Nuclear Reactor RA Safety Report, Vol. 12, Accidents during reactor operation; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 12, Akcidenti u dosadasnjem radu reaktora

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-11-01

This volume includes description and analysis of typical accidents occurred during operation of RA reactor in chronological order, as follows: contamination of primary coolant circuit; leakage of heavy water from the primary coolant loop; contamination of vertical experimental channel; air contamination in the reactor building and loss of circulation of the primary coolant; failures of the vacuum pump and spent fuel packaging device; rupture of the spent fuel element cladding; dethronement's of capsule for irradiation of fuel element; rupture of the vertical experimental channel and contamination of the surroundings; swelling of a fuel element; appearance of deposits on the surface of the fuel elements cladding. The last chapter describes similar accidents occurred on nuclear reactors in the world. [Serbo-Croat] Ova knjiga sadrzi hronoloski pregled i analizu karakteristika akcidenata u dosadasnjem radu reaktora RA: kontaminacija primarnog kola hladjenja; isticanje teske vode is primarnog kola hladjenje; kontaminacija eksperimentalnog vertikalnog kanala; kontaminacija vazduha u hali reaktora i prestanak cirkulacije primarnog hladioca; otkaz vakum pumpe i uredjaja za prepakivanje ozracenog goriva; proboj kosuljice ozracenog gorivnog elementa; dehermetizacija kapsule za ozracivanje nuklearnog goriva; proboj eksperimentalnog vertikalnog kanala i kontaminacija prostorija; bubrenje gorivnog elementa; pojava taloga na kosuljicama gorivnih elemenata. Poslednje poglavlje opisuje udese na koji su se dogodili na nuklearnim reaktorima u svetu.

RA research nuclear reactor operation in forced regime, Annex 5; Prilog 5 - Rad istrazivackog nuklearnog reaktora RA u forsiranom rezimu, Prvo saopstenje

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Mitrovic, S [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

1964-12-15

In order to increase the flux and experimental potentials of the RA reactor, properties of the reactor operating in the forced regime have been inspected four times, twice with the spent fuel (core C), and twice with partly fresh fuel (cores E and F). Forced regime means power higher than nominal 6.5 MW. From the analyses of technology parameters during operation in the forced regime at power levels of 7 and 11 MW, state and behaviour of the components, efficiency of the biological protection and other parameters it was concluded that the reactor operation is possible at power levels of 10 MW during a whole year, and under certain conditions even longer operation at power levels up to 15 MW. This paper examines the reactor operation conditions in the forced regime and gives conclusions related to real increase of the experimental possibilities, isotope production and economic factors. Radi povecanja fluksa i eksperimentalnih mogucnosti reaktora RA, cetiri puta su proverene osobine reaktora u forsiranom rezimu, tj. na snagama vecim od nominalne (6,5 MW) i to dva puta sa istrosenim gorivom (jezgro C) i dva puta sa delimicno svezim (jezgra E i F). Iz analize tehnoloskih parametara u toku eksperimentalno rada reaktora u forsiranom rezimu na snagama od 7 do 11 MW, stanja i ponasanja opreme, efikasnosti bioloske zastite i ostalih parametara, zakljucuje se da je moguc permanentan rad reaktora tokom cele godine na snagama do 10 MW, a pod izvesnim uslovima i duzi rad na snagama do 15 MW. U radu su diskutovani uslovi rada reaktora u forsiranom rezimu i donose se zakljucci o realnom povecanju eksperimentalnih mogucnosti, proizvodnje radioizotopa i o ekonomskim faktorima (author)

RA Research nuclear reactor Part 1, RA Reactor operation and maintenance in 1987; Istrazivacki nuklearni reaktor RA Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1987. godini

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Sotic, O; Martinc, R; Cupac, S; Sulem, B; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1987-12-15

RA research reacto was not operated due to the prohibition issued in 1984 by the Government of Serbia. Three major tasks were finished in order to fulfill the licensing regulations about safety of nuclear facilities which is the condition for obtaining permanent operation licence. These projects involved construction of the emergency cooling system, reconstruction of the existing special ventilation system, and renewal of the system for electric power supply of the reactor systems. Renewal of the RA reactor instrumentation system was initiated. Design project was done by the Russian Atomenergoeksport, and is foreseen to be completed by the end of 1988. The RA reactor safety report was finished in 1987. This annual report includes 8 annexes concerning reactor operation, activities of services and financial issues, and three special annexes: report on testing the emergency cooling system, report on renewal of the RA reactor and design specifications for reactor renewal and reconstruction. [Serbo-Croat] Reaktor RA nije radio usled zabrane Izvsnog veca Skupstine Srbije od 27. avgusta 1984. U cilju povecanja pouzdanosti rada reaktora a da bi se udovoljilo zakonskim propisima sto je uslov za dobijanje stalne dozvole za rad realizovana su tri velika zahvata na reaktoru RA. Ovi zahvati obuhvatili su izgradnju sistema za hladjenje jezgra reaktora u slucaju nuzde, rekonstukciju postojeceg sistema specijalne ventilacije i rekonstrukciju sistema napajanja elektricnom energijom neophodnih potrosaca reaktora RA. Zapoceti su radovi na modernizaciji intrumentacije reaktora RA, projekat je izradjen u sovjetskoj organizaciji Atomenergoeksport, a trebalo bi da se realizuje do kraja 1989. godine. U cilju povecanja prostora za skladistenje ozracenog nuklearnog goriva i njegovog efikasnijeg koriscenja, izradjen je su projekti za rekonstrukciju postojecih uredjaja za rukovanje gorivom, povecanje smestajnog kapaciteta i preciscavanje vode u bazenima za odlezavanje. Realizaija ovih

Work Breakdown Structure and Work Packages for Decommissioning the Nuclear Research Reactor VVR-S Magurele-Bucharest

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NONE

2013-06-15

The research reactor type VVR-S (tank type, water cooled, moderator and reflector, thermal power 2 MW, thermal energy 9.52 GWd) was put into service in July 1957, and in December 1997, was shut down. In 2002, the Romanian Government decided to put the research reactor into a permanent shutdown condition in order to start decommissioning. This nuclear facility had been used in nuclear research and radioisotope production for 40 years without any events, incidents or accidents. At the same site, in the immediate vicinity of the research reactor, there are many other nuclear facilities: a radioactive waste treatment plant, a tandem Van de Graaff heavy ion accelerator, a cyclotron, an industrial irradiator and a radioisotope production centre.

Nuclear Reactor RA Safety Report, Vol. 14, Safety protection measures; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 14, Sigurnosne zastitne mere

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-11-01

Nuclear reactor accidents can be caused by three type of errors: failure of reactor components including (1) control and measuring instrumentation, (2) errors in operation procedure, (3) natural disasters. Safety during reactor operation are secured during its design and construction and later during operation. Both construction and administrative procedures are applied to attain safe operation. Technical safety features include fission product barriers, fuel elements cladding, primary reactor components (reactor vessel, primary cooling pipes, heat exchanger in the pump), reactor building. Safety system is the system for safe reactor shutdown and auxiliary safety system. RA reactor operating regulations and instructions are administrative acts applied to avoid possible human error caused accidents. [Serbo-Croat] Uzroci udesa na nuklearnim reaktorima mogu se svrstati u jednu od sledece tri grupe: (1) otkaz pojedinih delova opreme, ukljucujuci mernu i kontrolnu instrumentaciju, (2) greske u pogonu i eksploataciji, (3) prirodne nepogode, katastrofe. Bezbednost i sigurnost u radu nuklearnog reaktora osiguravaju se odredjenim merama koje se preduzimaju pri njegovoj izgradnji i kasnije njegovoj elsploataciji. Te mere se mogu podeliti u sledece dve kategorije: (1) mere tehnicke zastite, i (2) administrativne mere. Mere tehnicke zastite sastoje se od barijere fissionih produkata, kosuljice gorivnih elemenata, primarnog kola reaktora RA (reaktorski sud, cevovod primarnog kola, toploizmenjivac u pimpi), zgrada reaktora. Sigurnosni sistem cini sistem za sigurnosno zaustavljanje reaktora i pomocni sigurnosni sistem. Kroz odgovarajuce propise i uputstva za rad na reaktoru RA primenjene su administrativne mere neophodne za sprecavanje udes koji bi mogao nastati kao posledica ljudskog faktora.

Nuclear Reactor RA Safety Report, Vol. 15, Analysis of significant accidents; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 15, Analiza znacajnih akcidenata

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-11-01

Power excursions of the RA reactor a mathematical model of reactor kinetic behaviour was formulated to describe power and temperature coefficients for both reactor fuel and moderator. Computer code TM-1 was written for analysis of possible reactor accidents. Power excursions caused by uncontrolled control rod removal and heavy water flow into the central vertical experimental channel were analyzed. Accidents caused by fuel elements handling were discussed including possible fuel element damage. Although the probability for uncontrolled radioactive materials release into the environment is very low, this type of accidents are analyzed as well including the impact on the personnel and the environment. A separate chapter describes analysis of the loss of flow accident. Safety analysis covers the possible damage of the outer steel Ra reactor vessel and the water screens which are part of the water biological shield. [Serbo-Croat] Radi analize dinamickog ponasanja reaktora RA u toku ekskurzije snage formulisan je matematicki model koji opisuje promene snage i temperature goriva i moderatora. Za analizu predpostavljenih akcidenata realizovan je racunarski program TM-1. Analizirane su ekskurzije snage usled nekontrolisanog izvlacenja kontrolnih sipki i punjenja centralnog vertikalnog eksperimentalnog kanala teskom vodom. Analizirani su akcidenti pri rukovanju nuklearnim gorivom ukljucujuci ostecenje nuklearnog goriva. Iako je verovatnoca za nekontrolisano rasturanje radioaktivnog materijala mala, analizirani su i ovakvi moguci akcidenti koji mogu uticati kako na osoblje reaktora tako i na okolinu. Posebno poglavlje obuhvata analizu akcidenta u slucaju prestanka cirkulacije primarnog hladioca. Analiza sigurnosti reaktora obuhvata i moguce ostecenje spoljasnjeg celicnog suda reaktora RA kao i vodenih ekrana koji su deo vodenog bioloskog stita.

Operation and maintenance of the RA nuclear reactor for 1977, Report Annex I; Rad i iskoriscenost reaktora RA u 1977. godini, izvestaj Prilog I

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Martinc, R; Stanic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1977-12-15

RA reactor operation plan was fulfilled, meaning 28583 MWh. In addition to 183 days of operation at full power, during 1977 the reactor was operated for 14 days at lower power level according to the demand of users. The utilization level of rector irradiation capability (neutron flux and time of operation) was 14%. This annex includes detailed statistical data about reactor operation, utilization, power level, savings concerned with new 80% enriched fuel. All the 9 vertical experimental channels were used for irradiation in the reactor core. Digression from the action plan were caused by refueling and demand od the users. There have been 11 safety shutdowns, of which 6 caused by power cuts, 4 due to failure of the instruments, and 1 due to earthquake in March 1977. [Serbo-Croat] Planirani rad reaktora na nominalnoj snazi ostvaren je u iznosu od 28583 MWh. U toku 1977. godine reaktor je radio 14 dana na manjim snagama i u posebnom eksperimentalnom rezimu na zahtev korisnika. Iskoriscenost kapaciteta reaktora za ozracivanje uzoraka (na bazi neutronskog fluksa i vremena rada reaktora) bila je 41%. Ovaj izvestaj sadrzi detaljne statisticke podatke o radu i iskoriscenosti reaktora, podatke o ustedi goriva prelaskom na 80% obogaceno gorivo. Korisceno je svih 9 vertikalnih eksperimentalnih kanala u aktivnoj zoni. Uzroci odstupanja od plana rada osim zamene goriva bili su zahtevi korisnika. Bilo je 11 sigurnosnih zaustavljanja, 6 usled nestanka napona, 4 usled kvarova opreme i instrumentacije, i 1 put usled zemljotresa u martu.

Operation, safety and utilization of the RA reactor in 1978 - Report; Prilog I - Rad, sigurnost i iskoriscenost reaktora RA u 1978. godini - Izvestaj

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Martinc, R; Stanic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1978-12-15

This report includes a review of work related to development of reactor operation capacities and increase of the RA reactor safety and economic operation. Statistical data about reactor operation and utilization are included as well. Introducing of the new 80% enriched fuel into the the reactor core enabled increase of the neutron flux, i.e. increase of its production capabilities. Safety and optimization analyses concerned with introduction of the new fuel have shown that the most safe and economic procedure was gradual introducing of the highly enriched fuel. This procedure was based on the concept of mixed core configuration with 2% and 80% enriched fuel elements. By applying this original concept the following significant savings were achieved: fuel elements savings, shortening of the annual period of reactor operation, savings in spent fuel casks, electric power savings, slowing down of heavy water degradation. [Serbo-Croat] Ovaj izvestaj sadrzi pregled o radu na razvoju eksploatacionih mogucnosti i povecanju sigurnosti i ekonomicnosti reaktora RA. Prilozeni su i statisticki podaci o radu i iskoriscenosti reaktora u 1978. godini. Uvodjenje novog 80% obogacenog goriva u jezgro reaktora omogucilo je povecanje neutronskog fluksa tj. povecanje njegovoh proizvodnih mogucnosti. Sigurnosne i optimizacione analize uvodjenja novog goriva pokazale su da je nasigurniji i najekonomicniji postupak postupnog uvodjenja visokoobogacenog goriva koji se zasniva na konceptu mesane resetke sa 2% i 80% obogacenim gorivom. Ovaj originalni koncept omogucio je da se postignu znatne ustede u gorivu, skracivanje godisnjeg rada reaktora, usteda sudova za odlaganje isluzenog goriva, usteda elektricne energije, usporavanje degradacije teske vode.

Measurement of zero power reactor dynamic response by cross correlation method; Merenje dinamickog odziva reaktora nulte snage kros korelacionom metodom

Energy Technology Data Exchange (ETDEWEB)

Kostic, Lj; Petrovic, M [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

1969-07-15

Pulse response is comprehensive description of linear system dynamics. In this paper, cross correlation method was used for measuring the response of zero power reactor. Reactor system was perturbed by pseudo-random signal, which was cross correlated with the reactor signal responding to this perturbation on the digital ZUSE Z-23 computer. Cross-correlation functions were measured for different positions of stochastic oscillator and ionization chamber in the critical system. From numerical processing of performed experimental data, it was concluded that a more powerful faster computer would be needed for processing statistical experiments. In that case it would be possible to obtain information about spatial effects in the reactor and propagation of neutron waves in the multiplication medium. Impulsni odziv je potpuni opis dinamike linearnog sistema. Za merenje impulsnog odziva nultog reaktora, u ovom radu, koriscena je kros korelaciona metoda. Reaktorski sistem je perturbovan pseudoslucajnim signalom, koji je u digitalnom racunaru ZUSE Z-23 kroskorelisan sa signalom odziva reaktora na ove perturbacije. Merene su kroskorelacione funkcije za razlicite polozaje stohastickog oscilatora i jonizacione komore u kriticnom sistemu. Iz numericki obradjivanih eksperimenta namece se kao zakljucak da bi za obradu statistickih eksperimenata kod nultih reaktora bio potreban racunar veceg kapaciteta i brzine. U tom slucaju bi se iz ovako postavljenog eksperimenta moglo doci i do informacija o prostornim efektima u reaktoru i prostiranju neutronskih talasa kroz multiplikativnu sredinu. (author)

Action plan during reactor shutdown in October 1965, Annex 5; Prilog br. 5 - Plan radova u toku stajanja reaktora u mesecu oktobru 1965. godine

Energy Technology Data Exchange (ETDEWEB)

Nikolic, M [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1965-12-15

The action plan of the division for reactor maintenance during reactor shutdown includes detailed list of tasks for mechanics, electronic and electrical equipment group during the reactor shutdown period in October 1965. It contains tasks for planned shutdown periods in September, August, July, May, April, March, and February 1965. [Serbo-Croat] Plan radova Odelenja odrzavanja reaktora RA za period stajanja reaktora u oktobru mesecu 1965. sadrzi detaljnu listu zadataka masinske grupe, elektro grupe i elektronske grupe. Ovaj prilog sadrzi i zadatke koji ce biti obavljeni tokom planiranih perioda kada je reaktor zaustavljen u septembru, avgustu, julu, junu, maju, aprilu, martu i februaru 1965.

Operation and maintenance of RA Reactor, Annual report 1977; Pogon i odrzavanje reaktora RA - Izvestaj o radu u 1977. godini

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Milosevic, M et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1977-12-15

During 1977, the RA Reactor was operated at nominal power of 6.5 MW for 183 days. Total production was 28582 MWh which is 10% higher than planned. Second phase of introducing the 80% enriched fuel was fulfilled according to the plan. This means that the reactor core will be filled with highly enriched fuel in 1978. Refueling was done three time during the past year. After completing the first phase of the fuel exchange which was related mostly to reactor safety, the second phase will be devoted to the more efficient increase of neutron flux . This second phase is of utmost importance because higher neutron flux will provide better and more efficient reactor application from economic point of view. This will justify the application of the new more expensive highly enriched fuel. The budget for reactor operation and maintenance is hardly enough to cover the maintenance of the components and instrumentation. During 1977 there were no accidents related nor incidents related to the instrumentation or related to radiation protection. [Serbo-Croat] Reaktor RA je u toku 1977. godine ostvario rad od 28583 MWh odnosno 183 dana rada na nominalnoj snazi, sto u odnosu na plan rada iznosi 10% vise od planiranog. Druga faza uvodjenja 80% obogacenog goriva izvrsena je prema planu sto znaci da ce se punjenje jezgra reaktora 80% gorivom zavrsiti u toku 1978. godine. Izvrsene su tri izmene goriva. Posle isteka prvog dela prelaznog rezima koji je usmeren na maksimalnu sigurnost reaktora preci ce se na drugi deo usmeren na vece i brze povecanje neutronskog fluksa. Druga faza je od izuzetnog znacaja jer ce omoguciti bolje i znatno ekonomicnije koriscenje reaktora i opravdati upotrebu novog i skupljeg goriva. Sredstva za pogon i odrzavanje reaktora RA su jedva dovoljna za odrzavanje neophodnog nivoa opreme. Akcidenata u toku 1977. godine nije bilo ni sa opremom ni u pogledu zastite od zracenja.

Lessons learned from 50 years period the storage of the spent fuel from nuclear research reactor VVR-S

International Nuclear Information System (INIS)

Dragusin, M.

2010-01-01

The nuclear research reactor VVR-S was commissioned in July 1957. This reactor is in permanent shutdown since December 1997 and will be decommissioned. The duration of the decommissioning project is 11 years. The first year of decommissioning project is 2010. The spent nuclear fuels resulting from the 40 years of operating the nuclear research reactor are stored under wet conditions. The chemical and physical water parameters monitored are: transparency, conductibility, pH, chloride content, oxygen content, temperature, dry residual content, Al, Mn, Mg, Fe, Vn, Cr. Residual dry content must be maintained in requested range in order to prevent degradation and corrosion both of the clads, assemblies and linen material of the ponds. Two types of the nuclear fuel assemblies were used: LEU type -EK-10 and HEU type S-36 Russian origin. All spent nuclear fuel assemblies HEU-S-36 type were repatriated in Russian Federation in June 2009 in safety and security conditions without any problems due of the wet storage, after 25 years storage in wet conditions. The spent nuclear fuel assemblies types LEU EK-10 were stored in wet conditions more than 50 years. This paper describes the lessons learned during the 50 years management of the spent nuclear fuel resulted from the operation the research reactor VVR-S. The management was based on the maintenance of water parameters by water filtration, using at all times air HEPA filter incorporated in technological ventilation system and by monitoring the level, temperature, physical and chemical parameters of the water storage from ponds and by controlling ponds linen physical integrity. Also we have used the discs having the same compositions with materials from assemblies stored in the same ponds, in order to verify degradation and corrosion phenomena induced due to the quality of storage water. The paper will described these results obtained by metallographic, visual, XRF analysis onto discs and dry residual samples from storage

Influence of absorbers on the reactivity of the reactor; Odredjivanje uticaja apsorbera na reaktivnost reaktora

Energy Technology Data Exchange (ETDEWEB)

Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1961-12-15

Influence of absorbers on the reactivity of the reactor was calculated by two-group diffusion theory applying corrections for boundary conditions derived from the transport theory because diffusion theory in not applicable in the vicinity of boundary surfaces especially in case of strong absorbers. This report shows the calculations of central absorber efficiency in the core with and without reflector, and efficiency of the group of absorbers randomly placed in the core. Approximation method for determining the efficiency of the absorber is described as well as numerical verification of results. Effective absorber dimensions and the influence of gaps on the reactor dimensions are shown. [Serbo-Croat] Uticaj apsorbera na reaktivnost reaktora racunat je primenom difuzione dvogrupne teorije uz korekcije kod primene granicnih uslova koje daje transportna teorija za efektivne dimenzije apsorbera posto difuziona teorija ne moze da primeni u blizini granicnih povrsina posebno kod jakih apsorbera. U ovom izvestaju dati su proracuni efektivnosti centralnog apsorbera u reflektovanom u nereflektovanom reaktoru, efektivnosti grupe proizvoljno ubacenih apsorbera. Dat je i prikaz aproksimativne metode za odredjivanje efektivnosti apsorbera kao i numericka provera rezultata. Prikazane su efektivne dimenzije apsorbera kao i uticaj supljina na kriticne dimenzije reaktora.

Experimental RA reactor operation with 80% enriched fuel - Program of experimental operation: a) Program of experimental operation with 80% enriched fuel at low power, b) contents of the experimental operation with 80% enriched fuel at higher power levels; Program probnog rada: a) Program probnog rada reaktora sa 80% obogacenim gorivom na malim snagama, b) sadrzaj programa probnog rada reaktora RA sa 80% obogacenim gorivom na vecim snagama

Energy Technology Data Exchange (ETDEWEB)

Martinc, R; Sotic, O; Skoric, M; Cupac, S; Bulovic, V; Maric, I; Marinkov, L [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1980-10-15

Highly enriched (80%) uranium oxide fuel was regularly used in the mixed reactor core with the 2% enriched fuel since 1976. The most important changes related to reactor operation, in comparison with the original design project were related to reactor core fuelling schemes. At the end of 1979 reactor was shutdown due to the corrosion coating noticed on some fuel elements and due to decrease quality of the heavy water. Subsequently the Sanitary inspector of Serbia has prohibited further reactor operation. Restart of the reactor will not be a simple continuation of operation. It is indispensable to perform complete experimental program including measurements of critical parameters at different power levels for the core with fresh 80% enriched fuel. The aim of this document is to obtain working permission and its contents are in agreement with the procedure demanded by the Safety Committee of the Institute. It includes results of optimization and safety analysis for the initial reactor core. Since the permission for restart is not obtained, a separate RA reactor safety report is prepared in addition to the program for experimental operation. This report includes: detailed program for reactor experimental operation with 80% enriched fuel in the core at low power levels, and contents of the experimental operation with 80% enriched fuel in the core at higher power levels. [Serbo-Croat] Od decembra 1976. godine redovno je korisceno 80% obogaceno gorivo u mesanoj resetki reaktorskog jezgra sa 2% obogacenim gorivom. Najvece izmene na reaktoru u odnosu na originalni projekat izvrsene su u nacinu rukovanja gorivom. Krajem marta 1979. godine obustavljen je rad reaktora usled naslaga na gorivnim elementima i loseg stanja teske vode. Naknadno je izdata zabrana za rad reaktora od strane Sanitarnog inspektora SR Srbije. Ponovno pustanje reaktora u rad nece biti jednostavan nastavak rada. Neophodno je da se izvede kompletan program merenja kriticnih parametara i drugih

Nuclear Reactor RA Safety Report, Vol. 1, Introduction; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 1, Uvod

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-11-01

Based on the agreement between governments of Socialist Federal Republic of Yugoslavia and USSR of January 28 1956, a contract was signed about construction of RA research reactor in the Boris Kidric Institute of nuclear sciences. Building of the RA reactor started in 1956, and has reached criticality in 1959. Since then it has been in almost permanent operation, except for five longer shutdown periods: in 1963 because of heavy water and primary coolant system contamination with cobalt; in 1970 because of transporting the heavy water to France for isotopic regeneration; in 1979/1980 and 1983 because of aluminium oxyhydrate deposition on the fuel element cladding in reactor active region; in 1985/1986 because of ventilation system reconstruction and construction of emergency core cooling system. RA reactor is a heavy water cooled and heavy water moderated research reactor. Since the beginning of its operation, 2% enriched metal uranium fuel was used. From 1976, 80% enriched uranium oxide fuel elements were used partially in some core regions and since 1981 the complete core was filled with this highly enriched fuel. RA reactor was designed to operate under normal conditions at 6.5 MW power and at 10 MW power under forced regime. As a powerful neutron source the reactor was meant to be used for research in the field of reactor and neutron physics, solid state physics, radiation chemistry, biology and radioactive isotopes production. RA reactor was build by Yugoslav companies based on USSR basic design project. Main components of the systems were produced in USSR. [Serbo-Croat] Na osnovu Sporazuma izmedju vlada SFRJ i SSSR od 28. januara 1956. godine, sklopljen je ugovor o izgradnji istrazivackog reaktora RA u Institutu za nuklearne nauke Boris Kidric u Vinci. Reaktor RA je poceo da se gradi 1956. godine, a kriticnost je postigao 1959. godine. Od tada je takoreci neprekidno bio u radu, izuzev u pet slucajeva duzeg stajanja: 1963. godine - zbog kontaminacije teske vode

Measurements at the RA Reactor related to the VISA-2 project - Part 1, Start-up of the RA reactor and measurement of new RA reactor core parameters; Fizicka merenja na reaktoru RA u vezi projekta VISA-2 - I deo, Pustanje u rad reaktora RA i merenje fizickih parametara novog jezgra reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Markovic, H [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1962-07-15

The objective of the measurements was determining the neutron flux in the RA reactor core. Since the number of fuel channels is increased from 56 to 68 within the VISA-2 project, it was necessary to attain criticality of the RA reactor and measure the neutron flux properties. The 'program of RA reactor start-up' has been prepared separately and it is included in this report. Measurements were divided in two phases. First phase was measuring of the neutron flux after the criticality was achieved but at zero power. During phase two measurements were repeated at several power levels, at equilibrium xenon poisoning. This report includes experimental data of flux distributions and absolute values of the thermal and fast neutron flux in the RA reactor experimental channels and values of cadmium ratio for determining the neutron epithermal flux. Data related to calibration of regulatory rods for cold un poisoned core are included. [Serbo-Croat] Svrha merenja je odredjivanje neutronskog fluksa u reaktoru RA. S obzirom na uvecani broj tehnoloskih kanala of 56 na 68 u vezi projekta VISA-2, bilo je potrebno ponovo dovesti reaktora RA do kriticnosti i izvrsiti merenja karakteristika fluksa neutrona. Posebno je pripremljen 'program pustanja u pogon reaktora RA', koji je sadrzan u ovom dokumentu. Program merenja bio je podeljen na dve faze. Prva faza je merenje fluksa pre podizanju reaktora na nominalnu snagu. Slicna merenja vrsena su i na vecim snagama u drugoj fazi, pod uslovima ravnoteznog zatrovanja reaktora ksenonom, jer se tada pokazuju izvesne promene u odgovarajucim karakteristikama fluksa neutrona. Ovaj izvestaj sadrzi merene vrednosti raspodele fluksa i apsolutne vrednosti termalnih i brzih neutrona kao i kadmijumskih odnosa koji su korisceni za odredjivanje fluksa epitermalnih neutrona. Opisana je kalibracija regulacionih sipki za hladan nezatrovan reaktor.

Regulations and instructions for RA reactor operation; Propisi i uputstva za pogon reaktora 'A'

Energy Technology Data Exchange (ETDEWEB)

NONE

1989-07-01

This regulatory guide consists of following 4 chapters: Description of the RA reactor, organization scheme, regulations for performing experiments; Regulations for staff on duty; Instructions for operating the vacuum systems, heavy water and helium systems; and evacuation in case of accident. [Serbo-Croat] Ovaj pravilnik sadrzi sledeca 4 poglavlja: Opis reaktora RA, sema organizacije rada, propisi za izvodjenje eksperimenata; Pravilnik za rad dezurnog osoblja; Uputstva za rada sa vakuum sistemima, sistemom teske vode, sistemom helijuma; evakuacija u slucaju udesa.

Lessons learned from the shut down, planning, and the preparatory activities of decommissioning the research reactor VVR-S Magurele, Bucharest

International Nuclear Information System (INIS)

Dragusin, M.; Copaciu, V.

2006-01-01

The nuclear research reactor type VVR was shut down in December 1997 after forty years of operation. The main characteristics of this reactor are: Thermal power 2 MW, Thermal energy - 9.59 GWhd, Average flux of thermal neutrons-10 13 n/cm 2 .s, nine horizontal channels, sixteen vertical exposure channels, three biological channels, reactor type tank, water used as a moderator, coolant and reflector. The reactor was used in research and radioisotope production. The reactor has been permanently shut down since April 2002, when the decommissioning was officially announced. Discussions regarding funding mechanisms for the conservation phase, and decommissioning (planning, preparatory activities, spent nuclear fuel management), have taken place since five years ago when the final decision of permanent shut down was taken. Quality management includes procedures for recording and archiving the lessons learned. The planning of decommissioning started in 1990 when the reactor was still operational. After fifteen years the regulatory body has not yet approved the decommissioning plan for the reactor. In this paper the following aspects are discussed: decommissioning strategy from safe enclosure to immediate dismantling, specific features of the site (treatment of radioactive waste near reactor) and state of decommissioning, use of the lessons learned in the planning of decommissioning for the other two small nuclear facilities situated in the same area with VVR-reactor: Sub critical Assembly 'HELEN' and Zero Power Critical Reactor RP-0, AFR ponds for spent nuclear fuel, other radiological facilities for radioisotopes production facilities radiation processing and accelerators. Preparatory activities for decommissioning have included: elaboration of a plan (inter alia, justification of the selected strategy, management of the radioactive waste in accordance with the waste acceptance criteria), reactor storage in parallel with the removal of the equipment and materials used in

Determination of reactor parameters in a simulated RA reactor lattice by measuring the reactivity level of heavy water in D{sub 2}O moderated RB reactor; Odredjivanje reaktorskih parametara u simuliranoj resetki reaktora RA merenjem reaktivnosti nivoa teske vode u D{sub 2}O moderiranom reaktoru RB

Energy Technology Data Exchange (ETDEWEB)

Takac, S M; Markovic, H D; Dimitrijevic, Z B [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

1974-07-01

Direct method for experimental determination of the neutron age {tau} in the reactor lattice is not developed. Fermi theory for determining {tau} by measuring the reactivity level of the heavy water can be applied for a limited number of reactor lattices. An attempt was made to apply this approach for a complex reactor core with side and upper reflector. As expected the obtained results were not satisfactory, and {tau} was determined by Dessauer formula which gives more realistic estimation of thermalization in the reactor cell. major discrepancies are resulting from the fact that the lower reflector was neglected. But it is possible to to determine {tau} for reactor core with reflectors by additional measurements of axial distribution and other experimental data for {tau}. This is quite tedious numerical procedure. Obtained experimental data for a number of reactor parameters are compared to the initial data of the RA reactor core showing very good agreement. [Serbo-Croat] Ekspeimentalna metoda za direktno odredjivanje starosti neutrona {tau}, u resetki reaktora do danas nije razvijena. Primenjena Fermijeova teorija za odredjivanje {tau} preko merenja reaktivnosti nivoa teske vode, ocigledno se moze koristiti samo na ogranicen spektar reaktorskih resetki. U ovom radu pokusano je da se vidi primenljivost iste u slozenom - bocno i odozdo - reflektovanom jezgru reaktora. Naravno dobijeni rezultati nisu zadovoljili, sto se i moglo ocekivati, pa je {tau} odredjen preko Dessauer-ove formule, sto daje daleko blizu sliku stvarnog stanja procesa termalizacije u celiji reaktora. Ocigledno vece neslaganje primenjene teorije dolazi od zanemarivanja donjeg reflektora u jezgru reaktora. Medjutim, dopnskim merenjem aksijalne raspodele i na osnovu ostalih eksperimentalnih podataka za {tau}, moguce je odrediti eksperimentalno reflektorski koeficijent za visestruko reflektovano jezgro reaktora, sto numericki predstavlja mukotrpan i dugotrajan rad na racunaru. Dobijeni

RA reactor operation and maintenance in 1990 with comparative evaluation from 1986-1990, Part 1; Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1990. godini, uz uporedni pregled za period 1986-1990. godina

Energy Technology Data Exchange (ETDEWEB)

Sotic, O; Cupac, S; Sulem, B; Zivotic, Z; Vasovic, B; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1990-12-15

During the previous period RA reactor was not operated because the Committee of Serbian ministry for health and social care has cancelled the operation licence in August 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. The new emergency cooling system and the reconstruction of the existing ventilation system were finished in 1989, the conditions for further reactor operation were fulfilled. In the meantime new licensing regulations adopted in 1988 were not demanding the mentioned conditions for reactors operated at power less than 10MW, RA reactor power being 6.5 MW. But the reactor could not be restarted due to planned renewal of the reactor instrumentation. It is planned to exchange the complete instrumentation by the end of 1991. Training program for the staff operating and maintaining the reactor components was prepared in 1985. Reconstruction, modification and construction of components demanded new documentation needed for further safe reactor operation. New version of RA reactor safety report was finished in 1986 according to the recommendations of IAEA and licensing regulations of Yugoslavia. In 1989, new documents were written covering regulations and instructions for reactor operation. The new reactor experimental loop was designed in 1986, and constructed and tested in 1990. All the reactor components were maintained by specific reactor services. Financing of the reactor remains a permanent problem. [Serbo-Croat] U proteklom periodu reaktor RA nije bio u pogonu zato sto je 30. jula 1984. godine Republicki komitet za zdravlje i socijalnu politiku republike Srbije, zabranio njegov rad zbog toga sto reaktor ne poseduje sistem za udesno hladjenje i ne poseduje odgovarajuce filtere u sistemu specijalne ventilacije. Radovi na izgradnji sistema za udesno hladjenje i rekonstrukciji postojeceg sistema specijalne ventilacije zavrseni su 1989. godine. Uslovi za nastavak rada reaktora

Activity of the Service for maintenance of mechanical equipment of the RA reactor - Report, Annex II; Prilog II - Rad sluzbe za odrzavanje masinske opreme reaktora RA u 1979. godini - Izvestaj -

Energy Technology Data Exchange (ETDEWEB)

Radivojevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1979-12-15

Service for mechanical components at the RA reactor includes: control and maintenance of utility components, mechanical workshop, hot cells and storage. Control and maintenance of main components covers: reactor core, heavy water system, technical water system, gas system. This service is responsible for the following auxiliary systems: transportation units; spent fuel storage pool; special ventilation system; personal protection appliances; hot cells. Maintenance of the reactor building, ventilation, heating, water supply, sewage, fire protection devices, gas and compressed air systems are included. [Serbo-Croat] Sluzba za masinsku opremu nuklearnog reaktora RA obuhvata: kontrolu i odrzavanje masinske opreme postrojenja, masinsku radionicu, vruce komore i prirucni magacin. Kontrola i odrzavanje osnovnih sistema obuhvata centralno telo reaktora, sistem teske vode, sistem tehnicke vode, gasni sistem. Pomocni sistemi koji spadaju u delatnost ove sluzbe su: transportna oprema, bazen za odlezavanje ozracenog goriva, sistem specijalne ventilacije, licna zastitna sredstva, vruce komore. Odrzavanje zgrade reaktora, ventilacije i grejanja, vodovoda i kanalizacije, opreme za protivpozarnu zastitu, instalacije gasa i komprimovanog vazduha su takode zadatak ove Sluzbe.

Regulations for the maintenance division of the RA reactor, Annex 6; Prilog 6 - Pravilnik poslovanja Odelenja odrzavanja i remonta reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Badrljica, R [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1965-12-15

The regulations for the Division of reactor maintenance include the organizational scheme, tasks of the Division, and operation procedures for all the staff members. [Serbo-Croat] Pravilnik o radu Odelenja za odrzavanje reaktora RA sadrzi opis organizacione strukture sluzbe, zadataka Odelenja, organizacije rada, nacin poslovanja za sve saradnike Odelenja.

Activity of the Service for maintenance of mechanical structures of the RA reactor - Report for 1980, Annex II; Prilog II - Rad sluzbe za odrzavanje masinske opreme reaktora RA - Izvestaj za 1980. god

Energy Technology Data Exchange (ETDEWEB)

Radivojevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1980-12-15

Service for mechanical components at the RA reactor includes: control and maintenance of utility components, mechanical workshop, hot cells and storage. Control and maintenance of main components covers: reactor core, heavy water system, technical water system, gas system. This service is responsible for the following auxiliary systems: transportation units; spent fuel storage pool; special ventilation system; personal protection appliances; hot cells. Maintenance of the reactor building, ventilation, heating, water supply, sewage, fire protection devices, gas and compressed air systems are included. [Serbo-Croat] Sluzba za masinsku opremu nuklearnog reaktora RA obuhvata: kontrolu i odrzavanje masinske opreme postrojenja, masinsku radionicu, vruce komore i prirucni magacin. Kontrola i odrzavanje osnovnih sistema obuhvata centralno telo reaktora, sistem teske vode, sistem tehnicke vode, gasni sistem. Pomocni sistemi koji spadaju u delatnost ove sluzbe su: transportna oprema, bazen za odlezavanje ozracenog goriva, sistem specijalne ventilacije, licna zastitna sredstva, vruce komore. Odrzavanje zgrade reaktora, ventilacije i grejanja, vodovoda i kanalizacije, opreme za protivpozarnu zastitu, instalacije gasa i komprimovanog vazduha su takode zadatak ove Sluzbe.

Results of environmental radiation monitoring and meteorology measurements (material prepared for obtaining the licence for RA reactor experimental operation); Rezultati merenja zracenja u okolini i rezultati meteoroloskih merenja (materijal pripremljen radi dobijanja dozvole za pustanje Reaktora RA u probni rad)

Energy Technology Data Exchange (ETDEWEB)

NONE

1980-10-15

According to the demands for obtaining the licence for restarting the Ra reactor and the experimental operation this document includes the radiation monitoring measured data in the working space and environment of the RA reactor, i.e. Boris Kidric Institute. The meteorology measured data are included as well. All the measurements are performed according to the radiation protection program applied actually from the first reactor start-up at the end of 1959. [Serbo-Croat] Saglasno zahtevu za dobijanje dozvole za ponovno pustanje u probni rad reaktora RA, ovaj dokument sadrzi rezultate merenja zracenja u okolini (radnoj i zivotnoj) reaktora RA odnosno instituta 'Boris Kidric' kao i podatke o meteoroloskim merenjima. Sve merenja rade se prema programu mera zastite od zracenja koje se sprovode prakticno od prvog pustanja reaktora u rad krajem 1959. godine.

Instructions for RA reactor decontamination - Annex 10; Prilog 10 - Uputstvo za dekontaminaciju Reaktora RA

Energy Technology Data Exchange (ETDEWEB)

NONE

1963-12-15

Instructions for RA reactor decontamination includes: action plan for decontamination of the heavy water system by 7% water solution of H{sub 3}PO{sub 4} + 2% CrO{sub 3} acid; description of the preparatory work including calculation of the pipes volume and installation of special pipes; detailed instructions for decontamination procedure. [Serbo-Croat] Uputstvo za dekontaminaciju Reaktora RA sadrzi: plan operacija za dekontaminaciju sistema teske vode 7% vodenim rastvorom kiseline H{sub 3}PO{sub 4} + 2% CrO{sub 3}; opis pripremnih radova ukljucujuci proracun zapremine covovoda i montiranje posebnih cevovoda; detaljno uputstvo za izvodjenje operacija pri dekontaminaciji.

RA reactor operation and maintenance, Annual report 1974; Pogon i odrzavanje reaktora RA - Izvestaj o radu u 1974. godini

Energy Technology Data Exchange (ETDEWEB)

Milosevic, D et al [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1974-12-15

During 1974, RA reactor was operated at nominal power for 194 days and 13 days at lower power levels. The total production was 30711 MWh which is 2.4% higher than planned. Practically there were no discrepancies from the plan. The reactor was used for irradiation and experiments according to the demand of 437 users. This report contains detailed data about reactor power and experiments performed in 1974. Total number of afety shutdowns was 11, of which 8 were caused by power cuts, and 3 due to human error. Maximum individual personnel exposure dose was 50% of the maximum permissible dose. There were no accidents during this year. Decontamination of surfaces was less than during previous years. About 805 m{sup 2} of surfaces and 178 objects were decontaminated. It was concluded that the successful operation in 1974 has a special significance taking into account the financial problems. [Serbo-Croat] Reaktor RA je u 1974. godini radio na nominalnoj snazi 194 dana i 13 dana na manjim snagama. Ukupni rad iznosio je 30711 MWh odnosno 1,4% vise od planiranog. Prakticno nije bilo odstupanja od plana rada. Reaktor je koriscen za ozracivanja i eksperimente za 437 korisnika. Ovaj izvestaj sadrzi detaljne podatke o radu i eksperimentima koji su obavljani. U toku godine bilo je 11 sigurnosnih zaustavljanja, od cega 8 zbog elektricnog napona i 3 usled greske osoblja. Ukupna doza ozracivanja ljudstva bila je manja nego prethodnih godina. Maksimalna doza po oveku bila je 50% manja od maksimalno dozvoljene doze. Nije bilo ni jednog akcidenta. Dekontaminirano je znatno manje povrsina nego ranijih godina, i sakupljeno manje otpada nego prethodnih godina, dok tecnih efluenata nije bilo. Zakljuceno je da uspesan rad reaktora u 1974. godini ima poseban znacaj kada se imaju na umu problemi finansiranja reaktora.

Nuclear Reactor RA Safety Report, Vol. 16, Maximum hypothetical accident; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 16, Maksimalni hipoteticki akcident

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-11-15

Fault tree analysis of the maximum hypothetical accident covers the basic elements: accident initiation, phase development phases - scheme of possible accident flow. Cause of the accident initiation is the break of primary cooling pipe, heavy water system. Loss of primary coolant causes loss of pressure in the primary circuit at the coolant input in the reactor vessel. This initiates safety protection system which should automatically shutdown the reactor. Separate chapters are devoted to: after-heat removal, coolant and moderator loss; accident effects on the reactor core, effects in the reactor building, and release of radioactive wastes. [Serbo-Croat] Sema granjanja za maksimalni hipoteticki akcident obuhvata osnovne elemente: pocetak akcidenta, faze razvoja akcidenta i stablo razvoja - sema potencijalnih akcidentnih tokova. Uzrok pocetka akcidenta je pucanje cevovoda primarnog rashladnog sistema jezgra, sistema teske vode. Gubitak primarnog hladioca izaziva pad pritiska u primarnom sistemu hladjenja na ulazu u reaktorski sud. Ovaj poremecaj pobudjuje sigurnosno kolo zastite koje automatski treba da prekine rad reaktora. Posebno je razmatrano generisanje zaostale snage, isticanje hladioca i moderatora, efekti akcidenta na jezgro, efekti u zgradi reaktora, oslobadjanje radioaktivnih produkata.

Independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels, Task 2.50.05; Nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u vertikalnim eksperimentalnim kanalima reaktora RA, Zad. 2.50.05

Energy Technology Data Exchange (ETDEWEB)

Stojic, M; Pavicevic, M

1964-07-01

This report contains the following volumes V and VI of the Project 'Independent CO{sub 2} loop for cooling the samples irradiated in RA reactor vertical experimental channels': Design project of the dosimetry control system in the independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels, and Safety report for the Independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels. Ovaj izvestaj sadrzi dva albuma zadatka 'Nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u vertikalnim eksperimentalnim kanalima reaktora RA', Zad. 2.50.05: Album V: Predprojekat sistema dozimetrijske kontrole u nezavisnom kolu CO{sub 2} za hladjenje uzoraka ozracivanih u VEK reaktora RA i Album VI: Izvestaj o sigurnosti za nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u VEK reaktora RA.

RA Research reactor, Part 1, Operation and maintenance of the RA nuclear reactor for 1986; Istrazivacki nuklearni reaktor RA, deo 1, pogon i odrzavanje nukleanog reaktora RA u 1986. godini

Energy Technology Data Exchange (ETDEWEB)

Sotic, O; Martinc, R; Cupac, S; Sulem, B; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1986-12-01

In order to enable future reliable operation of the RA reactor, according to new licensing regulations, three major tasks started in 1984 were fulfilled: building of the new emergency system, reconstruction of the existing ventilation system, and reconstruction of the power supply system. Simultaneously in 1985/1986 renewal of the instrumentation and reconstruction of the system for handling and storage of the spent fuel in the reactor building have started. Design projects for these tasks are almost finished and the reconstruction of both systems is expected to be finished until 1988 and mid 1989 respectively. RA reactor Safety report was finished according to the recommendations of the IAEA. Investments in 1986 were used for 8000 kg of heavy water, maintenance of reactor systems and supply of new components, reconstruction of reactor systems. This report includes 8 annexes concerning reactor operation, activities of services and financial issues. [Serbo-Croat] Sa ciljem da se obezbedi pouzdan rad reaktora RA a u skladu sa zakonskim propisima, zavrsena su tri velika zahvata zapoceta 1984: izgradnja novog sistema za udesno hladjenje, rekonstrukcija postojeceg sistema za ventilaciju, i modernizacija reaktorske instrumentacije. Istovremeno tokom 1985/1986. zapoceta je modernizacija instrumentacije i rekonstrukcija sistema za rukovanje i skladistenje iskoriscenog goriva u zgradi reaktora. Projekti za navedene radove su vec zavrseni ili su u zavrsnoj fazi, a ocekuje se da ce rekonstrukcija oba sistema biti zavrsena do kraja 1988. odnosno sredine 1989. godine. Izrada izvestaja o sigurnosti reaktora RA, prema preporukama MAAE zavrsena je 1986. Investiciona ulaganja na reaktoru Ra u 1986. iskoriscena su za: nabavku 8000 kg teske vode, za investiciono odrzavanje reaktorskih sistema i nabavku opreme, za rekonstrukciju reaktorskih sistema. Ovaj izvestaj sadrzi 8 priloga koji opisuju rad reaktora, rad strucnih sluzbi i finansiranje.

Experimental study of space dependent nuclear reactor kinetics - Progress report; Eksperimentalno proucavanje prostorno zavisne kinetike nuklearnih reaktora - Izvestaj o napredovanju

Energy Technology Data Exchange (ETDEWEB)

Obradovic, D; Petrovic, M [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

1966-11-15

This paper describes experimental study of space-time behaviour of nuclear reactors by local complex-periodic perturbation of the absorption cross section and by measuring the local reactor response to this perturbation. Perturbation was done by BOR-1 fast oscillator. Cross correlation between the response and the perturbation was done numerically after completing the measurement by using digital computer. Obtained experimental results are preliminary and are measured with significant errors which were analysed in this paper. Results show qualitative agreement with those obtained by theoretical model. This paper is the first progress report in this field in our country. U radu je opisan eksperimentalni prilaz proucavanju prostorno-vremenskog ponasanja nuklearnih reaktora, vrseci lokalnu slozeno-periodicnu perturbaciju apsorpcionog preseka i mereci lokalni odziv reaktora na tu perturbaciju. Perturbacija je vrsena brzim oscilatorom BOR-1. Kroskorelacija izmedju odziva i perturbacije vrsena je numericki posle obavljenog merenja upotrebom digitalne racunske masine. Dobijeni eksperimentalni rezultati imaju preliminarni karakter i odredjeni su sa znatnim eksperimentalnim greskama koje su, u radu analizirane. Izlozeni rezultati pokazuju kvalitativna slaganja sa teorijski dobijenim modelom. Ovaj rad predstavlja prvi izvestaj o napredovanju na ovoj problematici kod nas (author)

RA Research reactor Annual report 1981 - Part 1, Operation, maintenance and utilization of the RA reactor; Istrazivacki nuklearni reaktor RA, Deo 1 - Pogon, odrzavanje i eksploatacija reaktora u 1981. godini

Energy Technology Data Exchange (ETDEWEB)

Sotic, O; Milosevic, M; Martinc, R; Kozomara-Maic, S; Cupac, S; Radivojevic, J; Stamenkovic, D; Skoric, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1981-12-15

biggest difficulty was maintenance of reactor instrumentation. During 1981 the reactor was operated safely, there was no accident nor incident that would affect the safety of reactor personnel or the environment. The testing operation will be continued in 1982,and the experience so far shows that the program would be successfully fulfilled on the whole. [Serbo-Croat] Nuklearni reaktor RA prestao je sa radom nakon martovske kampanje 1979. godine usled pojave talozenja oksihidrata aluminijuma na kosuljicama gorivnih elemenata. Odgovarajucim resenjima Sanitarnog inspektorata Republickog sekretarijata za zdravje i socijalnu politiku SR Srbije i generalnog direktora Instituta za nuklearne nauke 'Boris Kidric', Vinca zabranjen je dalji rad reaktora sve dok se ne utvrde uzroci stvaranja oksihidrata aluminijuma i njihovog talozenja, preduzmu mere za njihovo uklanjanje i ne obezbede potrebni uslovi za normalan nastavak rada reaktora. Do kraja 1979. i tokom 1980. godine, nakon niza izvrsenih analiza i utvrdjivanja uzroka koji su doveli do zaustavljanja rada reaktora, izvrsene su sve neophodne pripreme za ponovno pustanje reaktora u rad. Polazeci od cinjenice da na reaktoru RA ne postoji sistem za hladjenje jezgra u slucaju udesa i da ne postoji adekvatan sistem za filtriranje potencijalno zagadjenog vazduha, a saglasno sa novim propisima o pustanju u rad i probnom radu nuklearnih objekata, Sanitarni inspektorat je doneo privremeno resenje kojim se dozvoljava pustanje reaktora u rad, tj. izvodjenje tzv. 'nultog eksperimenta' uz ogranicenje snage na 1% od vrednosti nominalne snage. Na osnovu dobijene dozvole, reaktor RA je ponovo pusten u rad 21. januara 1981. godine, kada je dostignuta kriticnost sa jezgrom sastavljenim iskljucivo od gorivnih elemenata od 80% obogacenog uranijuma. Eksperiment je zavrsen krajem marta, nakon cega je zatrazena dozvola za probni rad na vecim snagama i potom za rad na punoj snazi. Uzimajuci postojece stanje reaktora RA doneto je resenje kojim se

Twenty years of chemistry associated with the needs and utilization of nuclear reactors at the 'Boris Kidric' Institute of nuclear sciences, Vinca, Yugoslavia; Dvadeset godina hemije vezane za potrebe i koriscenje nuklearnih reaktora u Institutu za nuklearne nauke 'Boris kidric' i Vinci

Energy Technology Data Exchange (ETDEWEB)

NONE

1969-07-01

This publication covers nine review papers on the following topics related to the needs and utilization of nuclear reactors in the Boris Kidric Institute of nuclear sciences during previous twenty years: radiochemistry, hot atom chemistry, isotope production, spent nuclear fuel reprocessing, chemistry of transuranium elements; liquid radioactive waste processing, purification of reactor coolant water by inorganic ion exchangers, research related to deuterium concentration processes, and chemical dosimetry at the RA reactor. [Serbo-Croat] Ova publikacija obuhvata devet radova, po sledecim naslovima, a odnose se na potrebe i uslove nuklearnih reaktora u Institutu za nuklearne nauke 'Boris Kidric' tokom prethodnih dvadeset godina: radiohemija, hemija vruceg atoma, proizvodnja radioaktivnih izotopa, prerada isluzenog nuklearnog goriva, hemija transuranskih elemenata, obrada radioaktivnih otpadnih voda, preciscavanje vode za hladjenje nuklearnih reaktora pomocu neorganskih jonoizmenjivaca, istrazivanje procesa za koncentrovanje deuterijuma i hemijska dozimetrija reaktora RA.

Management of the radioactive waste resulting from the Romanian VVR-S research reactor decommissioning

International Nuclear Information System (INIS)

Ene, D.; Cepraga, D.G.

2002-01-01

The paper consists in a waste study of the Romanian VVR-S reactor which will be prepared for decommissioning operations after the permanent shutdown (23.12.1997). Calculations were carried out to determine the activity arising from neutron activation of structural materials inside the reactor, considering the design of the facility and its operating rules. To this end, the following method was used: i) Neutron flux distribution within the reactor was calculated using the DORT transport code, based on DLC23 shielding library relating to three cylindrical reference systems of the reactor structure: reactor core, horizontal tube and thermal column; ii) Calculation of the activity of each reactor component at different cooling times was performed by the ANITA2000 code, using the neutron flux, compositional data for each material and the power history of the reactor; iii) Unconditional clearance indexes for all material at various cooling times were calculated using the clearance levels defined in IAEA-TECDOC-855; iv) Total activities and masses by material type, within the waste category and for each decay time were calculated by summation of the data previously classified for each reactor component. The resulting activation inventory and waste masses, falling in IAEA defined waste categories are presented in the paper at periods of 100 days, and 6, 10, 25, and 50 years after reactor the shutdown. For some components of the reactor as: aluminum central vessel, the central iron shielding ring, the time behaviour of both the fin spatial activity distribution and the radionuclide contributions to the total activity are plotted in the paper. (author)

Operation and maintenance of the RA Reactor in 1985, Part 1, Annex B - Report of the Technology Service; Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1985. godini - Prilog B - Izvestaj o radu tehnoloske sluzbe

Energy Technology Data Exchange (ETDEWEB)

Martinc, R; Vukadin, Z; Stosic, O; Cupac, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1985-12-01

Technology service is established according to the need of unified technology control of the reactor, based on the organizational structure developed in USA, a part of which was applied at the Krsko NPP. Tasks of this service are: regular control and recording of operating reactor parameters under steady state and accidental conditions; control of chemical state of the reactor core (control of Ph values and electro conductivity of the heavy water and technical water); dosimetry parameters control and recording; safety and optimisation analyses when planning reactor core modifications; (changing the type of fuel, design of new components); cooperation with the reactor users during isotope production, activation analyses, application of neutron beams; participating in research programs; planning refueling. The most important task performed by this service was conversion of the core from 2% to 80% enriched fuel elements. A methodology for optimizing the reactor application was developed. Operation of the heavy water purification system, heavy water parameters, and operation of the gas system were controlled. Radiation and contamination levels in the working environment were measured, individual and collective doses. [Serbo-Croat] Tehnoloska sluzba uspostavljena je u skladu sa ispoljenim potrebama jedinstvene tehnoloske kontrole reaktora, oslanjajajucui se na organizacionu semu koja je razvijena u SAD, a cija je jedna varijanta primenjena na NE Krsko. Zadaci sluzbe su obavljanje sledecih zadataka: redovna kontrola i evidencija radnih parametara reaktora u redovnim i akcidentalnim uslovima; kontrola hemijskog rezima u reaktoru (kontrola PH vrednosti i elektroprovodnosti teske i tehnicke vode); kontrola i evidencija tehnicke dozimetrije; sigurnosne i optimizacione analize prilikom planiranja izmena na reaktoru (promene vrste goriva, izgradnja novih elemenata opreme); saradnja sa korisnicima reaktora prilikom prozivodnje izotopa, aktivacione analize, koriscenja

Nuclear Reactor RA Safety Report, Vol. 5, Reactor cooling systems; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 5, Hladjenje reaktora i pripadajuci sistemi

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-11-01

RA reactor cooling system enable cooling during normal operation and under possible accidental conditions and include: technical water system, heavy water system, helium gas system, system for heavy water purification and emergency cooling system. Primary cooling system is a closed heavy water circulation system. Heavy water system is designed to enable permanent circulation and twofold function of heavy water. In the upward direction of cooling it has a coolant role and in the downward direction it is the moderator. Separate part of the primary coolant loop is the system for heavy water purification. This system uses distillation and ion exchange processes. [Serbo-Croat] Sistemi za hladjenje reaktora RA obezbedjuju hladjenje u svim rezimima eksploatacije i potenijalno udesnim satnjim i obuhvataju: sistem tehnicke vode, sistem teske vode, gasni sistem helijuma, sistem za preciscavanje teske vode i sistem za akcidentalno hladjenje. Primarni sistem za hladjenje je zatvoreni cirkulacioni sistem teske vode. Specificnost sistema teske vode vezana je za neprekidnost cirkulacije i razlicite funkcije teske vode. U uzlaznom strujanju, teske vode ima ulogu hladioca a u silaznom ulogu moderatora. Poseban deo primarnog sistema predstavlja sistem za preciscavanje teske vode. Ovaj sistem koristi destilacioni i jonoizmenjivacki postupak.

The physics design of EBR-II; Physique du reacteur EBR-II; Fizicheskij raschet ehksperimental'nogo reaktora - razmnozhitelya EVR-II; Aspectos fisicos del reactor EBR-II

Energy Technology Data Exchange (ETDEWEB)

Loewenstein, W. B. [Argonne National Laboratory, Argonne, IL (United States)

1962-03-15

hexagonal del reactor los datos obtenidos en geometrias simples idealizadas, analiticas o experimentales. Se compara el rendimiento nuclear, incluso el de reproduccion, del reactor real con el del modelo teorico y se describen las variaciones a largo plazo de la reactividad y de la generacion de energia en la envoltura fertil, refiriendolas a los ciclos propuestos para el combustible y la envoltura fertil. La memoria formula consideraciones sobre la seguridad estudiando en particular la introduccion de indices de reactividad normales y anormales y la consecuencia de supuestos efectos de reactividad, que se basan en el comportamiento fisico de la aleacion combustible y de la estructura del reactor, asi como en la extrapolacion al sistema del EBR-II de los experimentos realizados con el conjunto TREAT. Por ultimo, examina el problema de la fusion del cuerpo del reactor EBR-II. (author) [Russian] Vychisleniya statisticheskogo, dinamicheskogo i dlitel'nogo rezhima reaktivnosti ehksperimental'nog o reaktora-razmnozhitel ya EBR-II dayutsya sovmestno s rezul'tatami i analizom ehksperimentov na reaktore EBR-II po dostizheniyu kritichnosti v sukhom sostoyanii i otdel'nykh ehksperimentov na reaktore ZPR-III. Osoboe vnimanie udelyaetsya problemam fizicheskogo rascheta reaktora, kotorye voznikayut posle opredeleniya printsipial'noj skhemy i do sooruzheniya ili vvoda reaktora v ehkspluatatsiyu. Opisyvayutsya analiz bezopasnosti reaktora i soobrazheniya po otsenke opasnostej, a takzheikh vliyanie na raschet reaktora. V doklade opisyvaetsya sposob ispol'zovaniya modeli EBR-II na osnovanii poluchennykh na reaktore ZPR-III dannykh, a takzhe dannykh sukhoj kritichnosti reaktora EBR-II. EHti ehksperimenty, ikh analiz i teoreticheskie vykladki yavlyayutsya osnovoj dlya opredeleniya fizicheskogo povedeniya reaktornoj sistemy. Bolee podrobno issleduyutsya ogranicheniya, prisushchie primeneniyu ehksperimental'nykh dannykh k rassmatrivaemo j ehnergeticheskoj reaktornoj sisteme. Syuda otnosyatsya

Operation and maintenance of the RA reactor, RA Research reactor. Annual report 1976; Pogon i odrzavanje reaktora RA, Izvestaj o radu u 1976. godini

Energy Technology Data Exchange (ETDEWEB)

Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1976-12-15

remonta do kojih je dolazilo zbog kvarova (nastalih zbog neizvrsavanja investicionog odrzavanja u toku poslednjih 6 godina) zatim nemogucnost ranijeg pocetka koriscenja novog goriva u reaktoru RA i istrosenosti rezervi starog 2% obogacenog goriva i na kraju zbog obimnog programa eksperimenata u oblasti sigurnosnih analiza vezanih za uvodjenje novog visokoobogacenog goriva u reaktor RA. Na reaktoru RA uspesno su izvrseni eksperimentalni i teorijski radovi u oblasti sigurnosnih analiza za prevodjenje reaktora RA na novo 80% obogaceno gorivo, krunisani eksperimentalnom kampanjom reaktora RA u decembru 1976, kojom se zavrsava 17-to godisnji period koriscenja 2% obogacenog goriva i otpocinje period koriscenja novog 80% obogacenog goriva u reaktoru RA. Ovaj uspeh je od izuzetnog znacaja za reaktor RA i njegove korisnike, jer ce rezultovati u povecanju osnovne proizvodnje neutronskog fluksa od 50%, pri porastu cene kostanja rada reaktora od oko 4%. Podnet je zahtev za konacno odobrenje prelaznog rezima za uvodjenje ovog goriva, kojim se postize usteda od najmanje 2 200 000 dinara. Ovim se obezbedjuje da u 1977. godini i dalje, rad reaktora ne bude vise ometan ''kriticnim'' ili drugim eksperimentima u vezi sa uvodjenjem novog goriva u reaktor. Izvrsen je obiman program remontnih i drugih radova veoma akutne prirode, koji takodje omogucuju nesmetan rad u 1977. godini. Neki od ovih radova nisu radjeni nikad ranije, a drugi nisu radjeni u proteklih 6 godina. Najzacajniji zahvati ove vrste bili su: nabavka Al-cevi od specijalne legure, izrada i montiranje tehnoloskoh kanala; obimno ispitivanje uzroka curenja spoljasnjeg suda; remont teskovodne pumpe; zamena dva vertikalna tehnoloska kanala. Nabavljena je osnovna oprema za izgradnju sistema za hladjenje u slucaju udesa. Izvrseno je opremanje vrucih komora reaktora RA.

Activity of the RA Reactor Physics group in 1980 - Definition of the Operation conditions for future safe and economical RA reactor operation with 80% enriched fuel; Prilog Ia - Rad sluzbe za fiziku reaktora RA u 1980. godini - Definisanje pogonskih uslova za dalji siguran i ekonomican rad reaktora RA sa 80% obogacenim gorivom

Energy Technology Data Exchange (ETDEWEB)

Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1980-12-15

During 1980. the RA reactor was not in operation. That is why this period was devoted to definition of operating conditions for further reactor operation with 80% enriched fuel. The fuel elements which were in the core at the moment of shutdown in March 1979will not be used again (388 80% enriched fuel elements, and 511 2% enriched fuel elements). The reactor will be operated only with 80% enriched fuel, staring with initiat core configuration with 440 elements on the borders gradually changing to equi;librium core with 720 fuel elements. The analyses were concerned with safety issues of future operation. [Serbo-Croat] Reaktor RA tokom 1980 godine nije radio. Zbog toga je ovaj period iskoriscen za intenzivan rad na definisanju pogonskih uslova za dalji rad reaktora sa 80% obogacenim gorivom. Gorivo sa kojim je reaktor prestao da radi marta 1979. godine (388 gorivnih elemenata 80% obogacenoh i 511 elementa 2% obogaceno) nece biti vraceno u jezgro, vec ce reaktor raditi samo sa 80% obogacenim gorivom, pocev od konfiguracije sa 440 elemenata na periferiji do ravnotezne konfiguracije sa 720 elemenata. Sve nalize su se bavile sigurnosnim aspektima rada reaktora sa visokoobogacenim gorivom u jezgru.

RA reactor action plan for 1977 - Annex VI; Prilog VI - Plan rada reaktora RA za 1977. godinu

Energy Technology Data Exchange (ETDEWEB)

NONE

1976-12-15

In the RA reactor action plan for 1977 it is foreseen that the reactor would be operated for 181 days, mostly at nominal power of 6.5 MW. It is planned to produce 28236 MWh in total. Five reactor core exchanges (refuelling) are planned. The plan includes time for repair of components as well as for cooling. [Serbo-Croat] Plan rada reaktora RA predvidja rad tokom 181 dana, vecim delom na nominalnoj snazi od 6,5 MW tokom 1977. godine. Planirano je da ukupni rad iznosi 28236 MWh. Planom je predvidjeno i pet izmena goriva kao i vreme potrebno za remont opreme i hladjenje.

Advanced fuel in the Budapest research reactor

International Nuclear Information System (INIS)

Hargitai, T.; Vidovsky, I.

1997-01-01

The Budapest Research Reactor, the first nuclear facility of Hungary, started to operate in 1959. The main goal of the reactor is to serve neutron research, but applications as neutron radiography, radioisotope production, pressure vessel surveillance test, etc. are important as well. The Budapest Research Reactor is a tank type reactor, moderated and cooled by light water. After a reconstruction and upgrading in 1967 the VVR-SM type fuel elements were used in it. These fuel elements provided a thermal power of 5 MW in the period 1967-1986 and 10 MW after the reconstruction from 1992. In the late eighties the Russian vendor changed the fuel elements slightly, i.e. the main parameters of the fuel remained unchanged, however a higher uranium content was reached. This new fuel is called VVR-M2. The geometry of VVR-SM and VVR-M2 are identical, allowing the use to load old and new fuel assemblies together to the active core. The first new type fuel assemblies were loaded to the Budapest Research Reactor in 1996. The present paper describes the operational experience with the new type of fuel elements in Hungary. (author)

RA reactor Action plan for 1978 - Annex VI; Prilog VI - Plan rada reaktora RA za 1978. godinu

Energy Technology Data Exchange (ETDEWEB)

NONE

1977-12-15

This annex include a detailed monthly action plan of the RA reactor for 1978. It was planned that the reactor will operate at nominal and lower power levels for 158 days. The plan is made with the aim to achieve same annual neutron flux as in 1977, which is somewhat higher then the annual production in the period from 1968-1975. [Serbo-Croat] Ovaj prilog sadrzi detaljan plan rada reaktora RA za 1978. godinu. Planirano je da reaktor radi na nominalnoj snazi of 6,5 MW i na manjim snagama ukupno 158 dana. Plan je napravljen tako da se ostvari godisnja proizvodnja neutronskog fluksa u obimu koji je relaizovan 1977. godine sto je nesto vise od godisnje proizvodnje u periodu 1968-1975.

Operation, maintenance and utilization of the RA reactor, Annual report for 1980; Pogon, odrzavanje i eksploatacija reaktora RA, Izvestaj o radu u 1980. godini

Energy Technology Data Exchange (ETDEWEB)

Milosevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1980-12-15

During 1980 the activities of RA reactor staff was conducted in two directions: repair works and determination of the state of the existing equipment; and preparing and constructing additional equipment and completing the documentation needed to fulfill the new legal regulations. preparation of the existing equipment for future operation was finished, but construction of the additional equipment (according to the regulations) is not done at planned rate due to different reasons such as lack of budget, administration, import. This report includes a chapter devoted to the analysis of the operation difficulties that caused prohibition of reactor operation as well as difficulties in achievement of the planned activities for 1980. Data about financial issues are included as well. [Serbo-Croat] U toku 1980. godine rad OOUR-a Nuklearni reaktor RA odvijao se u dva smera: remontnim radovima i utvrdjivanju stanja postojece opreme i u pripremi i ugradnji potrebne dodatne opreme i kompletiranju neophodne dokumentacije prema novim zakonskim propisima. Priprema postojece opreme za rad je u potpunosti izvrsena, dok se projekti i ugradnja dodatne opreme (prema zakonskim obavezama) ne odvija potrebnom brzinom zbog raznih objektivnih razloga, kao nedostatak sredstava, odobrenja, uvoza. Ovaj izvestaj sadrzi poglavlje posveceno analizi teskoca u radu koje su dovele do zabrane rada reaktora, i teskoca u realizovanju plana rada u 1980. godini, ako i podatke o finansiranju projekta 'pogon, odrzavanje i eksploatacija reaktora RA'.

Vicks VapoRub induces mucin secretion, decreases ciliary beat frequency, and increases tracheal mucus transport in the ferret trachea.

Science.gov (United States)

Abanses, Juan Carlos; Arima, Shinobu; Rubin, Bruce K

2009-01-01

Vicks VapoRub (VVR) [Proctor and Gamble; Cincinnati, OH] is often used to relieve symptoms of chest congestion. We cared for a toddler in whom severe respiratory distress developed after VVR was applied directly under her nose. We hypothesized that VVR induced inflammation and adversely affected mucociliary function, and tested this hypothesis in an animal model of airway inflammation. [1] Trachea specimens excised from 15 healthy ferrets were incubated in culture plates lined with 200 mg of VVR, and the mucin secretion was compared to those from controls without VVR. Tracheal mucociliary transport velocity (MCTV) was measured by timing the movement of 4 microL of mucus across the trachea. Ciliary beat frequency (CBF) was measured using video microscopy. [2] Anesthetized and intubated ferrets inhaled a placebo or VVR that was placed at the proximal end of the endotracheal tube. We evaluated both healthy ferrets and animals in which we first induced tracheal inflammation with bacterial endotoxin (a lipopolysaccharide [LPS]). Mucin secretion was measured using an enzyme-linked lectin assay, and lung water was measured by wet/dry weight ratios. [1] Mucin secretion was increased by 63% over the controls in the VVR in vitro group (p < 0.01). CBF was decreased by 35% (p < 0.05) in the VVR group. [2] Neither LPS nor VVR increased lung water, but LPS decreased MCTV in both normal airways (31%) and VVR-exposed airways (30%; p = 0.03), and VVR increased MCTV by 34% in LPS-inflamed airways (p = 0.002). VVR stimulates mucin secretion and MCTV in the LPS-inflamed ferret airway. This set of findings is similar to the acute inflammatory stimulation observed with exposure to irritants, and may lead to mucus obstruction of small airways and increased nasal resistance.

Experimental operation of the RA reactor with 4 fuel channels containing 80% enriched dispersion fuel - Operational Report; Radni izvestaj - Eksperimentalna kampanja reaktora RA sa 4 kanala sa 80% obogacenim disperzionim gorivom

Energy Technology Data Exchange (ETDEWEB)

Martinc, R; Milosevic, M; Cupac, S; Kozomara, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1976-12-15

usmerene su na prelazni rezim na bazi parcijalnog uvodjenja novog goriva u reaktor, tj. na reaktorsko jezgro sa dve vrste goriva. Cilj ovih analiza i priprema jeste obezbedjivanje svih uslova za siguran rad reaktora RA u prelaznom rezimu. Ove analize i pripreme su uglavnom kompletirane. Medjutim, nedostaje jos eksperimentalni podatak o utrosku goriva za odredjeni rad reaktora na nominalnoj snazi tj. o dnevnom padu ugradjenog viska reaktivnosti. Ovaj podatak neophodan je kod planiranja izmena goriva (kolicine svezeg goriva i ucestanosti izmena) u prelaznom rezimu. Do ovog podatka moze se doci samo putem normalnog rada reaktora u toku vremena znatno duzeg od vremena u kome se uspostavlja ravnotezno zatrovanje, kao vremena izmedju dva prelivanja D{sub 2}O kondenzata u aktivnu zonu RA. U tom smislu je planirana desetodnevna eksperimentalna kampanja u decembru 1976. U ovom izvestaju izlozeni su oni najznacajniji rezultati sigurnosnih analiza i priprema koji ukazuju na potpunu sigurnost rada reaktora tokom ove eksperimentalne kampanje, sa aspekta postovanja ogranicenja najvaznijih parametara koji uticu na sigurnost reaktora, kao sto su reaktivnost, toplotna i temperaturska ogranicenja za gorivo i za reaktor, itd. Podaci koji budu dobijeni iz ove eksperimentalne kampanje su od znacaja jer ce se na osnovu njih konacno definisati dalji protok svezeg novog goriva, tokom prelaznog rezima (author)

Purification of cooling water for nuclear reactors using ion exchangers; Preciscavanje vode za hladjenje nuklearnih reaktora pomocu neorganskih jonoizmenjivaca

Energy Technology Data Exchange (ETDEWEB)

Ruvarac, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1969-07-01

Zirconiumphosphate, zirconiumoxide and natural magnetite as inorganic substances with favourable adsorption properties were the subject of investigations dealing with problems of water purification for nuclear rector cooling. Study on adsorption of impurities form reactor water to 300 deg C and 100 Atm was done by specially constructed autoclaves. On the other hand, a pre-project covering a laboratory plant for investigation of inorganic ion exchangers under real dynamic conditions is given. In order to obtain necessary data on the basis of which techno-economical analyses regarding utilization of zirconiumphosphate, zirconiumoxide and magnetite for water purification is cooling the reactors types BWR and PWR, could be performed, systematic investigations of physical and chemical properties of these substances were commenced. Equilibrium constants have been determined for adsorption processes at different pH values, as well as under various temperatures. Obtained equilibrium constants were used for calculation of thermodynamic quantities {delta}H, {delta}G and {delta}S (author) [Serbo-Croat] Cirkonijumfosfat, cirkonijumoksid i prirodni magnet, kao neorganski materijali sa pogodnim adsorpcionim osobinama, bili su predmet istrazivanja vezanih za probleme preciscavanja vode za hladjenje nuklearnih reaktora. Izucavanje adsorpcije necistoca iz reaktorske vode do 300 deg C i 100 Atm vrseno je pomocu specijalno konstruisanog autoklava, a za ispitivanje neorganskih jonoizmenjivaca pri realnim dinamickim uslovima dat je idejni projekt jednog laboratorijskog postrojenja. Za dobijanje potrebnih podataka, na osnovu kojih se mogu napraviti tehno-ekonomske analize o koriscenju cirkonijumfosfata, cirkoijumoksida i magnetita za preciscavanje vode za hladjenje reaktora tipa BWR i PWR, zapoceto je sa sistematskim proucavanjima fizickih i hemijskih osobina pomenutih materijala, odredjivane su konstante ravnoteze za procese adsorpcije pri razlicitim pH vrednostima, kao i na razlicitim

Calculated activities of some isotopes in the RA reactor highly enriched fuel significant for possible environmental contamination - Operational report; Radni izvestaj - Proracun aktivnosti nekih izotopa u visokoobogacenom uranskom gorivu reaktora RA, znacajnih sa gledista moguce kontaminacije okoline

Energy Technology Data Exchange (ETDEWEB)

Bulovic, V; Martinc, R; Cupac, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1976-12-15

This report contains calculation basis and obtained results of activities for three groups of isotopes in the RA reactor 80% enriched fuel element. The following isotopes are included: 1) {sup 85m}Kr, {sup 87}Kr, {sup 88}Kr, {sup 131}J, {sup 132}J, {sup 133}J, {sup 134}J, {sup 135}J, {sup 133}Xe, {sup 138}Xe i {sup 138}Cs, 2) {sup 89}Sr, {sup 90}Sr, {sup 91}Sr, {sup 92}Sr, {sup 95}Zr, {sup 97}Zr, {sup 103}Ru, {sup 105}Ru, {sup 106}Ru, {sup 129m}Te, {sup 134}Cs, {sup 137}Cs, {sup 140}Ba, {sup 144}Ce, kao i 3) {sup 238}Pu, {sup 239}Pu i {sup 240}Pu. It was estimated that the fuel is exposed to mean neutron flux. The periodicity of reactor operation is taken into account. Calculation results are given dependent on the time of exposure. These results are to be used as source data for Ra reactor safety analyses. [Serbo-Croat] Izlozene su osnove i prikazani su rezultati izvedenog proracuna aktivnosti tri grupe izotopa u gorivnom elementu reaktora RA sa 80% obogacenim uranom - 235. Obuhvaceni su: 1) {sup 85m}Kr, {sup 87}Kr, {sup 88}Kr, {sup 131}J, {sup 132}J, {sup 133}J, {sup 134}J, {sup 135}J, {sup 133}Xe, {sup 138}Xe i {sup 138}Cs, zatim, 2) {sup 89}Sr, {sup 90}Sr, {sup 91}Sr, {sup 92}Sr, {sup 95}Zr, {sup 97}Zr, {sup 103}Ru, {sup 105}Ru, {sup 106}Ru, {sup 129m}Te, {sup 134}Cs, {sup 137}Cs, {sup 140}Ba, {sup 144}Ce, kao i 3) {sup 238}Pu, {sup 239}Pu i {sup 240}Pu. Pretpostavljeno je da se gorivo ozracuje na srednjem fluksu neutrona, a periodicnost rada reaktora je uvazavana. Rezultati proracuna, dati u numerickom obliku, sistematizovani su kao funkcija toka vremena ozracivanja goriva. Ovi rezultati bice korisceni kao izvorni podaci kod izrade sigurnosnih analiza za reaktor RA (author)

Study of the absorbers and gaps influence on the reactor reactivity, IZ-061-0071-1961; Ispitivanje uticaja apsorbera i supljina na reaktivnost reaktora, IZ-061-0071-1961

Energy Technology Data Exchange (ETDEWEB)

Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1961-12-15

It has been foreseen by the contract to study theoretically and experimentally the influence of the absorbers and gaps on the reactivity of the reactor. Within theoretical study it was planned to develop a method and find the approximation methods for calculations of these effects. Experimental part include development of equipment and performing the experiment at the RB reactor. Since it has not been possible to perform the experiment due to lack of heavy water, only the theoretical part of the task was completed with additional theoretical study of the VISA-1 experimental loop. This report includes the following annexes: influence of absorbers and gaps on the reactivity of the reactor, and calculation of flux depression in the VISA-1 loop. [Serbo-Croat] Ugovor predvidja teorijske i eksperimentalne radove u vezi ispitivanja uticaja apsorbera i praznina na reaktivnost reaktora. Za teorijski deo predvidjena je razrada metode i nalazenje aproksimativnih metoda za proracun ovih efekata. Eksperimentalni deo predvidja pripremu uredjaj i izvodjenje eksperimenata na reaktoru RB. S obzirom na nedostatak teske vode i nemogucnost izvodjenja eksperimenata, zadatak je obavljan samo teorijski a dodata mu je i teorijska obrada petlje VISA-1. Zadatak sadrzi sledece priloge: uticaj apsorbera i supljina na reaktivnost reaktora i proracun depresije fluksa u petlji VISA-1.

Safety report for the Independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels, Vol. VI; Album VI: Izvestaj o sigurnosti za nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u VEK reaktora RA

Energy Technology Data Exchange (ETDEWEB)

NONE

1964-07-01

First part of the safety report for the Independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels contains descriptions of the independent CO{sub 2} loop, system for regulation, measurement and control od the loop parameters, description of the dosimetry system, and the plan for testing the experimental device before start-up. Second part of this analysis describes the influence of of the experimental device on the reactor operation under steady state conditions as follows: influence of the head of the independent coolant loop on the reactivity of the reactor core and influence on the reactor temperature coefficient. Third part of the report includes the analysis of possible accidents during operation of the independent CO{sub 2} coolant loop in the reactor. Izvestaj o sigurnosti za nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u VEK reaktora RA sadrzi u prvom delu: opis nezavisnog kola CO{sub 2}, sistema za regulaciju, merenje i kontrolu parametara nezavisnog kola, sistema dozimetrijske kontrole i plan ispitivanja eksperimentalnih uredjaja pre pustanja u rad. Drugi deo ove analize obuhvata uticaj eksperimentalnog uredjaja na reaktor u normalnom rezimu rada i to: uticaj glave petlje nezavisnog kola CO{sub 2} za hladjenje uzoraka na reaktivnost reaktora i uticaj uredjaja na temperaturni koeficijent reaktora. Treci deo sadrzi analizu mogucih akcidenata u toku rada nezavisnog kola CO{sub 2} u reaktoru.

Maximum neutron flux at thermal nuclear reactors; Maksimum neutronskog fluksa kod termalnih reaktora

Energy Technology Data Exchange (ETDEWEB)

Strugar, P [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

1968-10-15

Since actual research reactors are technically complicated and expensive facilities it is important to achieve savings by appropriate reactor lattice configurations. There is a number of papers, and practical examples of reactors with central reflector, dealing with spatial distribution of fuel elements which would result in higher neutron flux. Common disadvantage of all the solutions is that the choice of best solution is done starting from the anticipated spatial distributions of fuel elements. The weakness of these approaches is lack of defined optimization criteria. Direct approach is defined as follows: determine the spatial distribution of fuel concentration starting from the condition of maximum neutron flux by fulfilling the thermal constraints. Thus the problem of determining the maximum neutron flux is solving a variational problem which is beyond the possibilities of classical variational calculation. This variational problem has been successfully solved by applying the maximum principle of Pontrjagin. Optimum distribution of fuel concentration was obtained in explicit analytical form. Thus, spatial distribution of the neutron flux and critical dimensions of quite complex reactor system are calculated in a relatively simple way. In addition to the fact that the results are innovative this approach is interesting because of the optimization procedure itself. [Serbo-Croat] Savremeni reaktori za fizicka i tehnoloska istrazivanja predstavljaju tehnicki komplikovanu i skupu masinu. Iz tog razloga su opravdana nastojanja da se podesnim rasporedom goriva u jezgru reaktora dodje do sto ekonomicnijeg rjesenja. U literaturi postoji vise radova, cak i konkretnih realizacija u vidu reaktora sa reflektorom u centru, koji se bave odredjivanjem takve prostorne zavisnosti koncentracije goriva koja pod odredjenim uslovima daje najveci neutronski fluks. Zajednicki nedostatak svih pomenutih rjesenja je u tome sto se polazi od pretpostavljenih prostornih distribucija

Opinion about difficulties of RA reactor operation under conditions of high activity of the heavy water system - Annex 2; Prilog 2 - Misljenje o teskocama eksploatacije reaktora RA u uslovima visoke aktivnosti teskovodnog sistema

Energy Technology Data Exchange (ETDEWEB)

Nikolic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1963-12-15

It was concluded that reactor the reactor operation is very dangerous for the reactor installation as well as safety of the staff under conditions of heavy water increased activity. Two fundamental arguments in favour of this conclusion are: insufficient possibility of reactor components inspection during maintenance and operation in the future period; difficulties in prevention of accidents that could occur is equally dangerous for the reactor facility and the environment. Cleaning and decontamination of the complete heavy water system is needed before the reactor operation starts in order to avoid possible failures or accidental events. [Serbo-Croat] Zakljuceno je da je eksploatacija reakora u uslovima postojece aktivnosti teskovodnog sistema veoma opasna po sam reaktor i po personal. Dva osnovna razloga u prilog ovog zakljucka su: nedovoljna mogucnost kontrole ispravnosti svih elemenata reaktora u toku remonta i ekspolatacije u predstojecem periodu; teskoca borbe sa udesima, koji bi se eventualno dogodili podjednako je opasna po instalaciju i okolinu. Pre no sto se nastavi sa daljom ekspolatacijom reaktora potrebno ciscenje, dekontaminacija sistema teske vode kako bi se izbegla moguca ostecenja ili akcidentalne situacije.

Independent CO{sub 2} loop for cooling the samples irradiated in vertical experimental channels of the RA reactor, Vol. I; Nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u vertikalnim eksperimentalnim kanalima reaktora RA, Album I

Energy Technology Data Exchange (ETDEWEB)

Pavicevic, M; Pavlovic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1963-06-15

Project 'independent CO{sub 2} loop for cooling the samples irradiated in the vertical experimental channels of the RA reactor' is presented in two volumes: volume I - head of the low temperature coolant loop for reactor RA, and volume II - Outer low-temperature reactor coolant loop. Volume I includes: the design specifications for the head of the low-temperature coolant loop, technical description, thermal calculation, calculations of mechanical loads, antireactivity and activation of the components of the coolant loop head, engineering schemes and drawings, cost estimation data. [Serbo-Croat] Projekat 'Nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u vertikalnim eksperimentalnim kanalima reaktora RA', sastoji se od dva albuma: album I - Glava niskotemperaturno rashladne petlje za reaktor RA, album II - Spoljno kolo niskotemperaturne rashladne petlje za reaktora. Album I sadrzi projektni zadatak glave niskotemperaturne petlje, tehnicki opis, termicki proracun, proracun mehanickih naprezanja, antireaktivnosti i aktivacije kontrukcionih elemenata glave petlje, konstrukcione seme i crteze glave petlje, predracun.

Wpływ czasu napowietrzania na pracę reaktora SBR i SBBR

Directory of Open Access Journals (Sweden)

Małgorzata Makowska

2016-06-01

Full Text Available W pracy przedstawiono efekty oczyszczania małych ilości ścieków w bioreaktorach porcjowych. Przebadano dwa równolegle pracujące reaktory, z czego jeden był klasycznym systemem SBR, a drugi to reaktor SBBR ze złożem ruchomym. Obydwa ciągi technologiczne oczyszczały taką samą ilość ścieków bytowych wstępnie podczyszczonych w piaskowniku. Trzy kolejne serie badań różniły się długością napowietrzania. Porównano pracę reaktorów w kolejnych seriach oraz analizowano wyniki uzyskane w obu systemach. Największą skuteczność usuwania związków węgla organicznego (jako ChZT i azotu (jako N-NH4 uzyskano w reaktorze SBBR w trzeciej serii badań (średnio odpowiednio 90 i 62%. Reaktor SBBR pracował bardziej stabilnie oraz usuwał na drodze biologicznej fosfor z największą średnią skutecznością 83% w serii trzeciej. Ścieki oczyszczone w tym reaktorze charakteryzowały się mniejszym stężeniem zawiesiny, co świadczy o skuteczniejszej pracy reaktora z wypełnieniem w fazie sedymentacji.

Track 4: basic nuclear science variance reduction for Monte Carlo criticality simulations. 6. Variational Variance Reduction for Monte Carlo Criticality Calculations

International Nuclear Information System (INIS)

Densmore, Jeffery D.; Larsen, Edward W.

2001-01-01

Recently, it has been shown that the figure of merit (FOM) of Monte Carlo source-detector problems can be enhanced by using a variational rather than a direct functional to estimate the detector response. The direct functional, which is traditionally employed in Monte Carlo simulations, requires an estimate of the solution of the forward problem within the detector region. The variational functional is theoretically more accurate than the direct functional, but it requires estimates of the solutions of the forward and adjoint source-detector problems over the entire phase-space of the problem. In recent work, we have performed Monte Carlo simulations using the variational functional by (a) approximating the adjoint solution deterministically and representing this solution as a function in phase-space and (b) estimating the forward solution using Monte Carlo. We have called this general procedure variational variance reduction (VVR). The VVR method is more computationally expensive per history than traditional Monte Carlo because extra information must be tallied and processed. However, the variational functional yields a more accurate estimate of the detector response. Our simulations have shown that the VVR reduction in variance usually outweighs the increase in cost, resulting in an increased FOM. In recent work on source-detector problems, we have calculated the adjoint solution deterministically and represented this solution as a linear-in-angle, histogram-in-space function. This procedure has several advantages over previous implementations: (a) it requires much less adjoint information to be stored and (b) it is highly efficient for diffusive problems, due to the accurate linear-in-angle representation of the adjoint solution. (Traditional variance-reduction methods perform poorly for diffusive problems.) Here, we extend this VVR method to Monte Carlo criticality calculations, which are often diffusive and difficult for traditional variance-reduction methods

Assessment of derived emission limits for radioactive effluents resulted from the decommissioning activities of the VVR-S nuclear research reactor

International Nuclear Information System (INIS)

Tuca, C.; Stochioiu, A.; Sahagia, M.; Gurau, D.; Dragusin, M.

2015-01-01

This paper presents complex studies on establishment of derived emission limits for potential radionuclides emitted as gaseous and liquid effluents, during the decommissioning activities (2nd and 3rd phases) of a nuclear research reactor, cooled and moderated with distilled water, type VVR-S, owned by the IFIN-HH. In the present paper there are described: the analysis methods and equipment used, the methodologies for calculating doses and the Derived Emission Limits (DEL), the experimentally measured activities of the representative radionuclides found in gaseous and liquid effluents resulted from decommissioning activities, as well as the effective derived limits of liquid and gaseous effluents, applying the calculation methodologies, specific to critical categories of exposed subjects. A constraint effective dose limit for a person from the critical group of 50 μSv/year was considered in calculations. From the comparison of the two series of values, measured released activities and DELs, there has been concluded that for the gaseous effluents they comply with the DELs, while in the case of liquid effluents they are higher and consequently they must be treated as liquid radioactive wastes. - Highlights: • The DELs for gaseous and liquid effluents in decommissioning were studied. • The impact on the environment and critical group was assessed. • Gamma-ray spectrometry was used to determine the radionuclide composition. • Based on the dosimetry models, the values of conservative DELs were calculated. • The DELs are compliant for gases, not for liquids; require the treatment as rad-waste

Radiation protection at the RA Reactor in 1989, Part -2, Decontamination, collection of treatment of fluid and solid radioactive waste, Annex 3; Deo 2 - Zastita od zracenja kod reaktora RA u 1989. godini, Dekontaminacija i intervencija, sakupljanje i obrada tecnih i cvrstih radioaktivnih otpadnih materija za potrebe reaktora RA - Prilog 3

Energy Technology Data Exchange (ETDEWEB)

Mandic, M; Vukovic, Z; Plecas, I; Knezevic, Lj; Lazic, S; Bacic, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1989-12-15

Certain amount of solid waste results from RA reactor operation, the mean quantity of which depends on the duration of reactor operation and related activities. During repair, when reactor is not operated as well under accidental conditions, the quantity of waste is higher, dependent on the type of repair and comprehensiveness of decontamination of the working surface, contaminated tools and components. The waste is sorted and packed on the spot where they appeared according to the existing regulations and principles of radiation protection with aim to minimize unnecessary exposure of the radiation protection personnel who deals with control, transport, radioactive waste treatment and decontamination. During exceptional operations (decontamination, repair, bigger volume of contaminated material, etc.) professional staff of the Radiation protection department gives recommendations and helps in planning the actions related to repair, sorting and packaging of radioactive waste in special containers, identification of the contaminants, etc. [Serbo-Croat] Tokom rada reaktora RA dolazi do stvaranja odredjenih cvrstih otpadnih materijala cija prosecna kolicina zavisi od vremena rada reaktora i aktivnosti koje se tamo obavljaju. Tokom remonta, kada reaktor ne radi kao i pri akcidentalnim situacijama nastaju vece kolicine otpadnih materijala koje zavise od obima i vrste remontnih operacija i obima dekontaminacije kontaminirane radne povrsine i kontaminiranog alata, predmeta, opreme, itd. Nastali otpadni materijali se razvrstavaju i pakuju na mestu nastanka prema odgovarajucim propisima u skladu sa principima zastite od zracenja i aspekta bezbednosti u cilju minimiziranja nepotrebnog ozracivanja ljudstva za preuzimanje, kontrolu, transport, naknadnu obradu RAO i dekontaminaciju. Pri nerutinskim operacijama (dekontaminacija, remont, kontaminiarni otpadni materijal velike zapremine i sl.), strucna sluzba Institita ZASTITA pruza strucne konsultacije i pomaze pri planiranju

RA Research nuclear reactor, Part I - RA nuclear reactor operation, maintenance and utilization in 1983; Istrazivacki nuklearni reaktor RA - Deo I - Pogon, odrzavanje i eksploatacija nuklearnog reaktora RA u 1983. godini

Energy Technology Data Exchange (ETDEWEB)

Sotic, O; Martinc, R; Kozomara-Maic, S; Cupac, S; Raickovic, N; Radivojevic, J; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1983-12-15

After regular shutdown in November 1982, inspection of the fuel elements from the RA reactor core which was done from December 1982 - February 1983 has shown that there are deposits of aluminium oxides on the surface of the fuel cladding. After restart The RA reactor was operated at power levels from 1.8 - 2 MW, with 80% enriched uranium dioxide fuel elements. It was found that there was no corrosion of the fuel element cladding and that it was not possible to find the cause of surface deposition on the cladding surfaces without further operation. It was decided to purify the heavy water permanently during operation and to increase the heavy water flow by operating two pumps. This procedure was adopted in order to decrease the possibility of corrosion. The Safety committee of the Institute has approved this procedure for operating the RA reactor in 1983. The core was made of 80% enriched fuel, critical experiments were done until June 1983, and after that the operation was continued at power levels up to 2 MW. [Serbo-Croat] Pregledom nuklearnog goriva iz tehnoloskih kanala reaktora RA koji je izvrsen u periodu decembear 1982-feburuar 1983. godine nakon zaustavljanja reaktora po isteku novembarske kampanje 1982. godine, ustanovljeno je da ponovo dolazi do stvaranja taloga u obliku hidratisanih oksida aluminiuma na kosuljicama gorivnih elemenata. Nakon ponovnog pustanja u rad, reaktor je do novembra 1981. godine neprekidno bio u pogonu na snagama 1,8 - 2 MW. Jezgro je bilo formirano iskljucivo sa od gorivnih elemenata sa 80% obogacenim uran dioksidom. Utvrdjeno je da kosuljica gorivnog elementa nije korodirala, i da se bez nastval rada ne moze utvrditi uzrok pojave taloga na povrsini kosuljice. Da bi se mogucnost korozije aluminjumskih komponenti u primarnom kolu raktora svela na sto manju meru odluceno je da se vrsi neprekidno preciscavanje teske vode i da se istovremeno poveca protok teske vode radom dve pumpe, Komitet za sigurnost Instituta odobrio je ovakav nacin

The training of the staff for work with radioactive materials and work on nuclear reactor in the Institute; Obuka kadrova za rukovanje radioizotopima i pogon nuklearnih reaktora u Institutu 'Boris Kidric' - Vinca

Energy Technology Data Exchange (ETDEWEB)

Milosevic, M; Mladjenovic, O; Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

1978-05-15

A short informational review of the activities in the 'Boris Kidric' Institute on the training courses for the use of radioactive materials and for operating nuclear reactors including power reactors. The survey of the courses is given in the enclosures. (author) Kratak informativni pregled delatnosti u IBK na kursevima za obuku kadrova u rukovanju readioaktivnim materijalima i pogonu nuklearnih reaktora, ukljucujuci reaktore snage. pregled kurseva i materijala za njih dati su u prilozima. (author)

Operation, maintenance and utilization of the RA reactor - Report on operation in 1979; Pogon, odrzavanje i eksploatacija reaktora RA, Izvestaj o radu u 1979. godini

Energy Technology Data Exchange (ETDEWEB)

Milosevic, M

1979-12-15

During 1979 the RA reactor was in operation only three months, i.e. only 24% of the planned activity was achieved. The reactor operation was interrupted in March due to problems that could not be solved by the existing equipment. Alkalinity of the heavy water resulting from the existing ammonia ions could not be removed by the existing distillation system. In addition deposition of aluminium oxyhydrate on the fuel elements was increased. This was noticed during routine control when the reactor was shutdown for refueling. The decision of the Director general of the Institute and sanitary Inspector followed, prohibiting further reactor operation. A separate chapter of this report is devoted to the analysis of the difficulties and possible solution of the problem in cooperation with the experts from different laboratories of the Institute. Aged and damaged instruments at the reactor were not exchange due to lack of budget. During the operation there were no accidents. [Serbo-Croat] U toku 1979. godine plan rada ostvaren je sa 24%, odnosno reaktor je radio samo prva tri meseca. U martu je doslo do prekida rada reaktora zbog pojave koja se nije mogla otkloniti postojecom opremom. Alkalnost teske vode, posledica prisustva amonijum jona, ne moze se odstraniti sistemom destilacije. Pored toga usled dotrajalosti opreme povecano je talozenje aluminijum oksihidroksida na gorivnim elementima. Ova pojava uocena je tokom rutinske kontrole prilikom izmene goriva a usledila je obustava rada resenjem Direktora i sanitarnog inspektora. Posebno poglavlje ovog izvestaja posveceno je analizi teskoca u radu i reaktora i resavanju nastalih problema sa gorivom u saradnji sa saradnicima drugih laboratorija Instituta. Dotrajali uredjaji i oprema nisu zamenjeni usled nedostatka sredstava. U toku rada nije bilo akcidenata.

Radiation protection at the RA Reactor in 1986, Part -2, Annex 2a, Radioactivity control of the RA reactor environment (atmospheric precipitations, dust, water, soil, plants, fruit...); Deo 2 - Prilog 2a - Kontrola radioaktivnosti okoline nuklearnog reaktora RA (padavine i slobodno natalozena prasina, vode, zemljiste, rastinje, voce...)

Energy Technology Data Exchange (ETDEWEB)

Ajdacic, N; Martic, M; Jovanovic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1986-12-01

Control of radioactivity in the biosphere in the vicinity of the RA reactor is part of the radioactivity control done regularly for the whole territory of the Vinca institute (report by the same authors included in this Annex). During 1986 control was conducted according to the plan until May 1, 1986 when a dramatic increase of the precipitations and all other samples from the biosphere was recorded. According to the measured data no significant changes have been found in the surroundings of the RA reactor, until April 29 1986. Since then more detailed control was conducted, the number of samples was increased, apart from standard measuring procedure of total beta activity measurements, gamma spectrometry of all samples was applied. High activity level of the following nuclides was found: Iodine, cerium,cesium, tellurium, ruthenium, barium, lanthanum, etc. As an example activity of ?1?3?1 I in one sample was 564{+-}5 kBq/m{sup 2}. [Serbo-Croat] Kontrola radioaktivnosti biosfere u okolini reaktora RA je deo kontrole radioaktivnosti koja se redovno vrsi za celokupnu teritoriju Instituta Vinca (izvestaj istih autora ukljucen je u ovaj Prilog). Tokom 1986. kontrola je ostvarivana prema planu do 1. maja 1986, kada je registrovano drasticano povecanje aktivnosti padavina i ostalih uzoraka biosfere. Prema rezultatima merenja, nisu registrovana znacajnija odstupanja u okolini reaktora RA sve do 29. aprila 1986. Od tada se vrse detaljnija merenja, broj uzoraka je uvecan, pored standardno primenjivane metode primenom merenja totalne beta aktivnosti uzoraka, svi uzorci su analizirani gama spektrometrijski. Enormno visoka kontaminacija uzoraka posle gamma spektrometrije pokazala je prisustvo aktivacionih i fisionih radionuklida medju kojima su bili: jod, cerijum, cesijum, rutenijum, barium lantan i drugi. Tako je na primer samo aktivnost I-133 iznosila 564{+-}5 kBq/m{sup 2}.

Radiation protection at the RA Reactor in 1996, Part -2, Annex 1, Control of the working environment, dosimetry and radiation protection; Prilog 1 - Zastita od zracenja kod reaktora RA u 1996. godini - Deo 2 - Kontrola radne sredine - dozimetrija i tehnicka zastita kod reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Pavlovic, R; Kalinic, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1996-12-01

This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. Previously initiated actions concerning future decision on the status of the RA reactor were continued during 1996. Actions in 1996 were focused to detailed analysis of the conditions of storing the spent fuel in the storage pools and preparing the documentation for decision making about the methods for the improvement of the mentioned conditions. It is stated that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radijacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. U trecem delu izvestaja navedeni su osnovni podaci o ukupnim kolicinama sakupljenog radioaktivnog materijala, ukupnoj velicini kontaminiranih i dekontaminiranih povrsina i broju dekontaminiranih predmeta. U 1996. godini nastavljena je akcija zapoceta prethodne

Data about operation and utilization of the RA in 1976 - Report, Annex I; Prilog I - Podaci o radu i iskoriscenosti reaktora RA u 1976. godini - Izvestaj -

Energy Technology Data Exchange (ETDEWEB)

Stanic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1976-12-15

, nemogucnost da se predvidi tacno vreme za eksperimente u okviru (uspesno provedenog) programa prevodjenja reaktora RA na novo visokoobogaceno gorivo, posto neki od ovih eksperimenata takodje nikada ranije nije radjen. Sem toga bilo je i nepredvidjenih vecih remontnih radova zbog nepredvidjenih kvarova. Planirano je 6 izmena goriva koje su ostvarene sa zakasnjenjem. Podaci o planiranom i ostvarenom radu reaktora u 1976. godini prikazani su u ovom izvestaju kao i podaci o prekidu rada. Kracih prekida i sigurnosnih zaustavljanja je bilo 12 u ukupnom trajanju od 64 casa. Reaktor je radio na nominalnoj snazi od 6.5 MW. Akcidenata vecih razmera nije bilo, medjutim dva slucaja mogu se opisati kao akcidentalne situacije po nacinu kako su nastali. Prvi je prskanje cevi kod lezaja teskovodne pumpe a drugi kontaminacija hale i hodnika nastala prilikom pripreme masine za izmenu goriva (izlivanje teske vode). Ovaj prilog sadrzi i podatke o koriscenju eksperimentalnog prostora i iskoriscenosti reaktora.

Research reactor RB, technical characteristics and experimental possibilities; Zbornik radova, Konferencija o koriscenju nuklearnih reaktora u Jugoslaviji

Energy Technology Data Exchange (ETDEWEB)

Sotic, O; Vranic, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

1978-05-15

Nuclear research reactor RB tn the Nuclear Engineering Laboratory at the Institute of Nuclear Sciences 'Boris Kidric' in Vinca is the first reactor system built in Yugoslavia in 1958. In this report, the basic technical characteristics of this reactor are described, as well as the experimental possibilities it offers to the users. Its relatively simple construction and flexibility enables direct measurements of a series of physical parameters, and the absence of the biological protection shield makes it very useful for Various biological and other irradiations and dosimetric measurements Where strong neutron source is required. (author) Istrazivacki nuklearni reaktor RB u Laboratoriji za nuklearnu energetiku i tehnicku fiziku Instituta za nuklearne nauke 'Boris Kidric' u Vinci je prvi reaktorski sistem izgradjen u Jugooslaviji 1958. godine. U ovom radu opisane su osnovne tehnicke karakteristike tog reaktora, kao i mogucnosti za izvodjenje eksperimenata koje on pruza korisnicima. Njegova relativno jednostavna konstrukcija i fleksibilnost omogucavaju da se na njemu izvrse direktna merenja niza fizickih parametara, a s druge strane odsustvo bioloskog zastitnog omotaca cini ga veoma pogodnim za razna bioloska i druga ozracivanja, a takodje i dozimetrijska merenja gde se zahteva snazan izvor neutrona. (author)

RA reactor operation in 1991, Part 1; Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1991. godini

Energy Technology Data Exchange (ETDEWEB)

Sotic, O; Cupac, S; Sulem, B; Zivotic, Z; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1992-01-01

pouzdan rad reaktora i skladu sa novim zakonskim propisima, u toku 1991. zavrseni su radovi na izgradnji sistema za udesno hladjenje, rekonstrukciju postojeceg sistema specijalne ventilacije i rekonstrukciji sistema za napajanje elektricnom energijom. Zapoceti su radovi na modernizaciji instrumentacije reaktora ali njegova realizacija u 1991. godini kasni usled zastoja u isporuci opreme iz Sovjetskog saveza. Izradu ove opreme finansira Medjunarodna agencija za atomsku energiju kroz ugovor sklopljen decembra 1988. godine sa moskovskom firmom Atomenergoexport, ali je MAAE privremeno zabranila isporuke opreme Jugoslaviji iz politickih razloga. Kontrola i odrzavanje opreme, kao i potrebni remontni radovi izvrsavani su redovno u zavisnosti od raspolozivosti rezervnih delova. Obuka postojeceg osoblja sprovodi se redovno ali nedostatak sredstava onemogucava prijem novih radnika sto bi bilo neophodno za rad u smenama i redovno odrzavanje.

Veeravalli Venkata Ranga Varadachari (1925-2007)

Digital Repository Service at National Institute of Oceanography (India)

Murty, C.S.

(NIO) on 1 January 1966. VVR shifted his place of work from Cochin to Goa, and continued to serve NIO till his retirement in July 1985. For his research and organizational abilities, VVR was honoured with a D Sc by the University of Jabalpur...) and contributed to the preparation of the document on ‘Ocean Sciences for the year 2000’ published by IOC/UNESCO. At NIO, VVR played a key role in organiz- ing the four Indian scientific expeditions to Antarctica from 1981 to 1984, and NIO received the status...

Temperature measurement of the reactor materials samples irradiated in the fuel channels of the RA reactor - Annex 16; Prilog 16 - Merenje temperature uzoraka reaktorskih materijala ozracivanih u gorivnim kanalima reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Nikolic, M; Djalovic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

1964-12-15

Reactor materials as graphite, stainless steel, magnox, zirconium alloys, etc. were exposed to fast neutron flux inside the fuel elements specially adapted for this purpose. Samples in the form ampoules were placed in capsules inside the fuel channels and cooled by heavy water which cools the fuel elements. In order to monitor the samples temperature 42 thermocouples were placed in the samples. That was necessary for reactor safety reasons and for further interpretation of measured results. Temperature monitoring was done continuously by multichannel milivoltmeters. This paper describes the technique of introducing the thermocouples, compensation instruments, control of the cold ends and adaptation of the instruments for precision (0.5%) temperature measurement in the range 30 deg - 130 deg C; 30 deg - 280 deg C and 30 deg - 80 deg C. Ozracivanje uzoraka materijala za izgradnju reaktora kao sto su grafit, nerdjajuci celik, magnox, legure cirkonijuma, aluminijuma itd. vrseno je u fluksu brzih neutrona unutar samih gorivnih elemenata koji su specijalno adaptirani za ovu svrhu. Uzorci u vidu ampula smesteni su u kapsulu od aluminijuma i postavljeni unutar kanala gde su hladjeni cirkulacijom teske vode koja hladi same gorivne elemente. U cilju kontrole temperature uzoraka radi bezbednosti samog reaktora, kao i radi kasnije interpretacije rezultata ispitivanja radijacionog ostecenja materijala, ugradjeno je 42 termopara u uzorke. Kontrola temperature je vrsena kontinualno visekanalnim registratorima. U radu je prikazana tehnika izvodjenja termoparova, kompenzacionih vodova, kontrola hladnih krajeva i prilagodjenje instrumentacije za merenje i registraciju temperature sa tacnoscu 0,5% u opsezima 30 deg - 130 deg C; 30 deg - 280 deg C i 30 deg - 80 deg C (author)

Radiation protection at the RA Reactor in 1997, Part -2, Annex 1, Control of the working environment, dosimetry and radiation protection; Prilog 1 - Zastita od zracenja kod reaktora RA u 1997. godini - Deo 2 - Kontrola radne sredine - dozimetrija i tehnicka zastita kod reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Pavlovic, R; Kalinic, S [Vinca Institute of Nuclear Sciences, Beograd (Serbia and Montenegro)

1997-12-01

This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. Previously initiated actions concerning future decision on the status of the RA reactor were continued during 1997. Actions in 1997 were focused to detailed analysis of the conditions of storing the spent fuel in the storage pools and preparing the documentation for decision making about the methods for the improvement of the mentioned conditions. After adopting the procedures, detailed preparations, and purchasing the needed equipment, the first phase of remedial action, the removal of the sludge from the bottom of the spent fuel storage pool was started in September 1997. It is stated that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radiacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. U trecem delu izvestaja navedeni

RA reactor operation and maintenance in 1994, Part 1; Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1994. godini

Energy Technology Data Exchange (ETDEWEB)

Sotic, O; Cupac, S; Sulem, B; Zivotic, Z; Mikic, N; Tanaskovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1994-12-01

During the previous period RA reactor was not operated because the Committee of Serbian ministry for health and social care has cancelled the operation licence in August 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. The planned major tasks were fulfilled: building of the new emergency cooling system, reconstruction of the existing ventilation system, and renewal of the reactor power supply system. The existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Renewal of the reactor instrumentation was started but but it is behind the schedule because the delivery of components from USSR was stopped for political reasons. The spent fuel elements used from the very beginning of reactor operation are stored in the existing pools. Project concerned with increase of the storage space and the efficiency of handling the spent fuel elements has started in 1988 and was fulfilled in 1990. Control and maintenance of the reactor instrumentation and tools was done regularly but dependent on the availability of the spare parts. Training of the existing personnel and was done regularly, but the new staff has no practical training since the reactor is not operated. Lack of financial support influenced strongly the status of RA reactor. [Serbo-Croat] U proteklom periodu reaktor RA nije bio u pogonu zato sto je 30. jula Republicki komitet za zdravlje i socijalnu politiku republike Srbije, zabranio njegov rad zbog toga sto reaktor ne poseduje sistem za udesno hladjenje i ne poseduje odgovarajuce filtere u sistemu specijalne ventilacije. Zavrseni su radovi na izgradnji sistema za udesno hladjenje, rekonstrukciji postojeceg sistema specijalne ventilacije i rekonstrukciji sistema za napajanje elektricnom energijom. Zapoceti su radovi na modernizaciji, odnosno zameni instrumentacije reaktora ali njegova realizacija kasni

Safety analysis for testing operation of the RA reactor in the Boris Kidric Institute, Vinca; Analiza sigurnosti rada reaktora 'RA' za probni rad u Institutu za nuklearne nauke 'Boris Kidric' - Vinca

Energy Technology Data Exchange (ETDEWEB)

Milosevic, M et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1980-09-15

This safety report covers detailed description of the RA reactor core, reactor components, coolant system, control system, safety system, reactor building including site characteristics. A separate chapter is devoted to radiation protection and radioactive waste management. Organizational structure od the reactor staff as well as training program are included. The last chapter includes detailed emergency plans for three accidents classified in three categories. [Serbo-Croat] Ovaj izvestaj sadrzi detaljan opis reaktora RA, sistema za hladjenje, kontolno-sigurnosnog sistema, elektricnog sistema, zgrade sa instalacijama, ukljucujuci karakteristike lokacije. Posebno poglavlje opisuje sistem zastite od zracenja i rukovanje radioaktivnim otpadom. Opisana je organizacija rada i program obuke osoblja. Poslednje poglavlje sadrzi detaljan plan mera za slucaj udesa klasifikovanih u tri kategorije.

RA Reactor; Reaktor RA

Energy Technology Data Exchange (ETDEWEB)

NONE

1989-07-01

This chapter includes the following: General description of the RA reactor, organization of work, responsibilities of leadership and operators team, regulations concerning operation and behaviour in the reactor building, regulations for performing experiments, regulations and instructions for inserting samples into experimental channels. [Serbo-Croat] Ovo (prvo) poglavlje sadrzi sledece: Opis reaktora RA; semu organizacije rada i rukovodjenja; prava i duznosti direktora i rukovodioca pogona reaktora, propise o rezimu rada i kretanja u zgradi reaktora, propise o izvodjenju eksperimenata, propise o unosenju uzoraka u eksperimentalne kanale reaktora.

Power Reactor Design at Zero Power; Etudes de Reacteurs de Puissance, au Moyen de Machines de Puissance Zero; Konstruktsiya ehnergeticheskogo reaktora nulevoj moshchnosti; Diseno de Reactores Generadores con Ayuda de Reactores de Potencia Nula

Energy Technology Data Exchange (ETDEWEB)

Redman, W. C.; Plumlee, K. E.; Baird, Q. L. [Argonne National Laboratory, Argonne, IL (United States)

1964-02-15

revela que el Laboratorio de Argonne ha venido basindose ampliamente en los sistemas exponenciales y criticos para llevar a cabo sus trabajos en materia de estudio de reactores. Los autores sugieren el papel futuro de estos sistemas al resumir brevemente los programas de trabajo, en curso de ejecucion o en proyecto, mediante los reactores de potencia nula que actualmente existen en Argonne y los que ese Laboratorio proyecta construit. (author) [Russian] Rjalis- sledovatel'skih reaktorov dlja central'nyh jelektrostancij, reaktorov v kachestve dvigate- lej, reaktorov dlja proizvodstva izotopov i ispytatel'nyh reaktorov byl issledovan na Argonskih reaktorah nulevoj moshhnosti, a svjazannye jeksponencial'nye i chisto kriticheskie sborki pozvolili poluchit' osnovnye dannye. Dlja togo, chtoby dat' nagljadnoe predstavle- nie o poslednih jeksperimentah i prodemonstrirovat' bol'shoe raznoobrazie dannyh o kon- strukcii reaktora, kotorye mozhno poluchit' v sistemah s maloj plotnost'ju nejtronnogo poto- ka, rassmatrivajutsja sledujushhie jeksperimental'nye programmy: 1. Izuchenie svojstv torievo-uranovogo topliva v tjazheloj vode s osobym uporom na trebova- nija, pred{sup j}avljaemye k konstrukcii vtoroj aktivnoj zony dlja Argonskogo jeksperimental'- nogo kipjashhego reaktora. 2. Maket predpologaemogo issledovatel'skogo reaktora s vysokoj plotnost'ju nejtronnogo potoka dlja podtverzhdenija raschetov konstrukcii, vybora optimal'noj geometrii i ocenki vlijanija vygoranija topliva. 3. Opredelenie harakteristik raspredelenija jenergii i vlijanija na reaktivnost' zatoplenija toplivnogo jelementa dlja kombinirovannyh ispytanij kipjashhego reaktora s peregrevom. 4. Konstrukcija aktivnoj zony proizvodjashhego plutonij reaktora-razmnozhitelja na bystryh nejtronah na urane - 235 s natrievym ohlazhdeniem kak pervoj zagruzki dlja Argonskogo jeksperimental'nogo reaktora-razmnozhitelja II. 5. Issledovanie harakteristik reaktora s vzaimodejstvujushhimi zonami na teplovyh i byst- ryh nejtronah. Pri

Theoretical analysis of nuclear reactors (Phase I), I-V, Part V, Determining the fine flux distribution; Razrada metoda teorijske analize nuklearnih reaktora (I faza) I-V, V Deo, Odredjivanje fine raspodele fluksa

Energy Technology Data Exchange (ETDEWEB)

Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1962-07-15

Mono energetic neutron transport equation was solved by Carlson numerical method in cylindrical geometry. S{sub n} code was developed for the digital computer ZUSE Z23. Neutron flux distribution was determined for the RA reactor cell by applying S{sub 4} approximation. Reactor cell was treated as D{sub 2}O-U-D{sub 2}O system. Time of iteration was 185 s. Resena je transportna monoenergetska jednacina numerickom metodom Carlsona u cilindricnoj geometriji. Razvijanje S{sub n} kod za digitalnu masinu ZUSE-Z 23. Odredjena je raspodela fluksa u celiji reaktora RA S{sub 4} aproksimacijom. Celija je tretirana kao D{sub 2}O-U-D{sub 2}O. Vreme iteracije je 185 sec (author)

Measurements of neutron flux in the RA reactor; Merenje karakteristika neutronskog fluksa u reaktoru RA

Energy Technology Data Exchange (ETDEWEB)

Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1961-12-15

This report includes the following separate parts: Thermal neutron flux in the experimental channels od RA reactor; Epithermal neutron flux in the experimental channels od RA reactor; Fast neutron flux in the experimental channels od RA reactor; Thermal neutron flux in the thermal column and biological experimental channel; Neutronic measurements in the RA reactor cell; Temperature reactivity coefficient of the RA reactor; design of the device for measuring the activity of wire. [Serbo-Croat] Ovaj izvestaj sadrzi sledece referate: Fluks termalnih neutrona u eksperimentalnim kanalima reaktora RA; Fluks epitermalnih neutrona u eksperimentalnim kanalima reaktora RA; Fluks brzih neutrona u eksperimentalnim kanalima reaktora RA; Fluks termalnih neurona u termalnoj koloni i bioloskom eksperimentalnom kanalu; Neutronska merenja u elementarnoj celiji reaktora RA; Temperaturni koeficijent reaktivnosti reaktora RA; Projekat uredjaja za merenje radioaktivnosti zice.

Operating Experience with the BR-5 Reactor; Experience acquise aupres du reacteur BR-5; Opyt ehkspluatatsii reaktora BR-5; Experiencia practica con el reactor BR-5

Energy Technology Data Exchange (ETDEWEB)

Lejpunskij, A. I.; Kazachkovskij, O. D.; Pinkhasik, M. S.; Aristarkhov, N. N.; Karpov, A. V.; Larin, E. P.; Efimov, I. A.

1963-10-15

remontnykh rabot na radioaktivnom zhidkometallicheskom konture reaktora na bystrykh nejtronakh BR-5. Osveshchayutsya voprosy ehkspluatatsii reaktora posle dostizheniya proektnogo 2%-nogo vygoraniya topliva pri nalichii nekotorogo narusheniya plotnosti otdel'nykh teplovydelyaptsikh ehlementov. Provoditsya opyt po razgruzke aktivnoj zony, issledovaniyu sostoyaniya i germetichnosti teplovydelyaptsikh ehlementov, dezaktivatsii oborudovaniya i truboprovodov I radioaktivnogo kontura posle dostizheniya 5% vygoraniya topliva. (author)

Radiation protection at the RA Reactor in 1990, Part -2, Control of the working environment, dosimetry and radiation protection, Annex 1; Deo - 2, Zastita od zracenja kod reaktora RA u 1990. godini, Prilog 1 - Kontrola radne sredine - dozimetrija i tehnicka zastita kod reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Ninkovic, M; Raicevic, J; Bjelanovic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1990-12-15

This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. It was found that the individual dose from external exposure during previous ten months was less than 2.5 mSv, and that single exposures of the staff was less than 1/10 of the annual dose limit. Comparison with the data for previous five years shows that the exposures in 1990 were lower than during past five years. It is stated that there has been no accident that would result in significant surface contamination. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radijacionih merenja. Dati su takodje rezultati merenja sadrzaja radioaktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. U trecem delu izvestaja navedeni su osnovni podaci o ukupnim kolicinama sakupljenog radioaktivnog materijala, ukupnoj velicini kontaminiranih i dekontaminiranih povrsina i broju dekontaminiranih predmeta. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila manja od 2,5 mSv a da su pojedinacna izlaganja radnog

Radiation protection at the RA Reactor in 1989, Part -2, Annex 1, Control of the working environment, dosimetry and radiation protection; Zastita od zracenja kod reaktora RA u 1989. godini - Deo 2, Prilog 1 - Kontrola radne sredine - dozimetrija i tehnicka zastita kod reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Ninkovic, M; Bjelanovic, J; Glodic, S; Raicevic, J; Pavlovic, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1989-12-15

This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. It was found that the individual dose from external exposure during previous ten months was less than 4.0 mSv, and that single exposures of the staff was less than 1/10 of the annual dose limit. Comparison with the data for previous five years shows that the exposures in 1989 were lower than during past five years. It is stated that there has been no accident that would result in significant surface contamination. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radijacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. U trecem delu izvestaja navedeni su osnovni podaci o ukupnim kolicinama sakupljenog radioaktivnog materijala, ukupnoj velicini kontaminiranih i dekontaminiranih povrsina i broju dekontaminiranih predmeta. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila manja od 4,0 mSv a da su pojedinacna izlaganja radnog

State of decommissioning process in Romania

International Nuclear Information System (INIS)

Ciuculescu, C.

2002-01-01

In Romania, there are several installations that arrived at the decommissioning stage. These installations are: VVR-S research reactor, Sub critical Assembly HELEN, and Zero Power Reactor (RP-0). In this paper, the methods the Romanian Regulatory Body is developing the legal framework for decommissioning process of nuclear installations are described. There is a draft of decommissioning norms for research reactors. This regulation provides each stage of decommissioning and requirements for decommissioning plan. Also, CNCAN has evaluated and made requirements for completion of a VVR-S research reactor decommissioning plan submitted by IFIN-HH. Further, the reasons for which the decommissioning plan was rejected and requirements that the owner of VVR-S research reactor must fulfil in order to receive decommissioning licence are presented. (author)

Project RA Research nuclear reactor - Annual report 1993 with comparative review for the period 1991 - 1993; Projekat Istrazivacki nuklearni reaktor RA - Izvestaj za 1993. godinu, uz uporedni pregled za period 1991 - 1993

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-12-15

Research reactor RA Annual report for year 1993 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. First part includes 8 annexes describing reactor operation, activities of services for maintenance of reactor components and instrumentation, financial report and staffing. The ninth separate annex deals with the feasibility of RA reactor applications. Second part of the report is devoted to radiation protection issues and contains 4 annexes with data about radiation control of the working environment and reactor environment, description of decontamination activities, collection of radioactive wastes, and meteorology data. [Serbo-Croat] Godisnji izvestaj o radu nuklearnog reaktora RA za 1993. godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA. Prvi deo sadrzi 8 priloga, koji opisuju rad reaktora i poslove sluzbi za odrzavanje opreme i komponenti, finansijski izvestaj, kadrovsku strukturu osoblja reaktora. Poseban prilog razmatra mogucnosti koriscenja istrazivackog reaktora RA. Drugi deo izvestaja o poslovima zastite od zracenja sadrzi 4 priloga sa podacima radijacione kontrole radne sredine i okoline reaktora, opis poslova dekontaminacije i sakupljanja radioaktivnih materija, kao i meteoroloske podatke.

Report of the Service for maintenance of mechanical structures - Annex 2; Prilog 2 - Rad sluzbe za odrzavanje masinske opreme

Energy Technology Data Exchange (ETDEWEB)

Radivojevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1976-01-15

This Annex 2 describes the organizational structure and activities of the Service for maintenance of the mechanical structures of the RA reactor, inspection and maintenance of of reactor components, workshop and storage of spare parts at the reactor. Mechanical structures of the RA reactor included are: heavy water system, gas systems, technical water system, reactor core, and transportation equipment. [Serbo-Croat] Pored opisa organizacije rada sluzbe za odrzavanje masinske opreme reaktora RA, ovaj prilog sadrzi: podatke o stanju, reviziji i remontu masinske opreme reaktora RA, prirucne radionice i magacina. Masinska oprema reaktora RA obuhvata: sistem teske vode, gasne sisteme, sistem tehnicke vode, centralno telo reaktora, transportnu opremu.

RB research nuclear reactor - Annual report for 1986, I - III; Istrazivacki nuklearni reaktor RB (Izvestaj o radu u 1986. godini), I-III

Energy Technology Data Exchange (ETDEWEB)

Markovic, H; Pesic, M; Vranic, S; Petronijevic, M; Jevremovic, M; Ilic, I [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

1987-07-01

This report includes data concerning the RB reactor operation in 1986, state of the reactor components, data about the employed personnel and the database of experimental and other reactor related devices. It is made of 3 parts: Engineering description and operation of the RB reactor including dosimetry, reactor staff data and financial report; Reactor facility components and maintenance; RB reactor operation and utilization in 1986. Izvestaj pokazuje podatke o radu reaktora RB u toku 1986. godine, stanje reaktorske opreme, podatke o angazovanom osoblju na reaktoru i datoteku sa podacima o eksperimentalnoj i drugoj opremi reaktora RB. Sastoji se od 3 dela: tehnicki opis, pogon i rad reaktora, oprema postrojenja i njeno odrzavanje, koriscenje reaktora u 1986. godini.

Radiation protection at the RA Reactor in 1985, Part -2, Annex 1, Radioactivity control of working environment, dosimetry; Deo 2 - Zastita od zracenja kod reaktora RA u 1985. godini - Prilog 1 - Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Ninkovic, M; Bjelanovic, J; Minincic, Z; Komatina, R; Raicevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1985-12-01

This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted to 8.2 mSV during past 10 months. Individual exposures for 7/10 of the personnel were less than 1/10 of the annual permissible exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. The last part analyzes accidents occurred at the reactor during 1985. It was found that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radiacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila 8.2 mSv, a da su pojedinacna izlaganja vise od 7/10 radnog osoblja bila manja od 1/10 godisnje granicne vrednosti. Dati su takodje uporedni podaci o

Resonance absorption of nuclear gamma radiation; Absorption par resonance des rayons gamma; Rezonansnaya absorbtsiya i rasseyanie yadernogo gamma-izlucheniya; Absorcion por resonancia de las radiaciones gamma en los nucleos

Energy Technology Data Exchange (ETDEWEB)

Hanna, S S; Perlow, G J [Argonne National Laboratory, Argonne, IL (United States)

1962-01-15

radiacion do resonancia con y sin polarizacion. Estos estudios les han conducido a una interpretacion de la estructura hiperfina en funcion de las propiedades de los estados nucleares y de la interaccion hiperfina en el hierro. Tambien han investigado los efectos de un campo magnetico externo sobre la estructura hiperfina. Por otra parte, la absorcion por resonancia en el {sup 57}Fe permitio estudiar la relacion entre la cronologia de la desintegracion de im estado nuclear y el espectro de la radiacion observada. Se realizaron observaciones detalladas sobre el espectro de las radiaciones de resonancia filtradas, en funcion del tiempo, en condiciones muy diversas. (author) [Russian] Kak pokazal Messbauehr, ispuskanie i pogloshchenie yadernogo izlucheniya bez otdachi yadra obespechivaet prostoj metod izucheniya vzaimodejstviya yader s ehlektromagnitnym izlucheniem i, chto ochen' vazhno, yavlyaetsya chrezvychajno chuvstvitel'nym sredstvom issledovaniya bol'shogo kolichestva fizicheskikh zadach. V sluchae yader zheleza-57 sozdaetsya ves'ma blagopriyatnoe polozhenie, tak kak v ehtom sluchae rezonansnoe pogloshchenie mozhet ispol'zovat'sya v kachestve ochen' chuvstvitel'nogo detektora izmeneniya chastoty ehlektromagnitnogo izlucheniya. Detal'no izuchalos' rezonansnoe pogloshchenie v zheleze-57. Intensivnost' pogloshcheniya, forma i liniya sdviga nablyudalis' v zavisimosti ot temperatury. Polyarizatsiya radioaktivnogo izlucheniya nablyudalas' posredstvom ehksperimentov s namagnichennymi istochnikami i poglotitelyami. Sverkhtonkij spektr rezonansnoj radiatsii analizirovalsya s polyarizatsiej i bez nee. EHti issledovaniya priveli k tolkovaniyu sverkhtonkoj struktury v otnoshenii svojstv yadernykh sostoyanij i sverkhtonkogo vzaimodejstviya v zheleze. Bylo rassmotreno takzhe vliyanie vneshnego magnitnogo polya na sverkhtonkuyu strukturu. Rezonansnoe pogloshchenie v zheleze-57 bylo ispol'zovano dlya izucheniya svyazi mezhdu razvitiem raspada yadernogo sostoyaniya vo vremeni i spektrom

Nondestructive analysis of RA reactor fuel burnup, Program for burnup calculation base on relative yield of {sup 106}Ru, {sup 134}Cs and {sup 137}Cs in the irradiated fuel; Nedestruktivno odredjivanje izgaranja goriva reaktora RA, Program za izracunavanje izgaranja na osnovu relativne zastupljenosti {sup 106}Ru, {sup 134}Cs i {sup 137}Cs u ozracenom gorivu

Energy Technology Data Exchange (ETDEWEB)

Bulovic, V F [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

1971-07-01

Burnup of low enriched metal uranium fuel of the RA reactor is described by two chain reactions. Energy balance and material changes in the fuel are described by systems of differential equations. Numerical integration of these equations is base on the the reactor operation data. Neutron flux and percent of Uranium-235 or more frequently yield of epithermal neutrons in the neutron flux, is determined by iteration from the measured contents of {sup 106}Ru, {sup 134}Cs and {sup 137}Cs in the irradiated fuel. The computer program was written in FORTRAN-IV. Burnup is calculated by using the measured activities of fission products. Burnup results are absolute values. Sagorevanje maloobogacenog uranskog metalnog goriva reaktora RA je opisano dvema lancanim reakcijama. Energetski bilans i materijalne promene u gorivu su opisane sistemima diferencijalnih jednacina. Numericka integracija jednacina se vrsi na osnovu podataka u dinamici rada reaktora. Fluks reaktorskih neutrona i procenat urana-235 ili ucesce epitermalnih neutrona u fluksu, odredjuje se iterativno na osnovu izmerenog sadrzaja {sup 106}Ru, {sup 134}Cs i {sup 137}Cs u ozracenom gorivu. Program je napisan u FORTRAN-u IV u jednom bloku, bez podprograma. Izracunavanje izgaranja je zasnovano na izmerenim kolicnicima aktivnosti fisionih produkata. Rezultati izgaranja imaju apsolutni karakter (author)

Report of the Technology Service - Annex B; Prilog B - Izvestaj o radu tehnoloske sluzbe

Energy Technology Data Exchange (ETDEWEB)

Martinc, R; Cupac, S; Vukadin, Z; Stosic, T; Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1986-12-01

This report describes the organisational structure of the technology service and its activities and tasks: routine control of reactor parameters and cooperation with the reactor users; development of methodology of reactor control and its application; control of heavy water and gas system operation; dosimetry measurements of contamination in the reactor building; technical aspects of radiation protection; decontamination and accident analysis. Separate chapter describes building of the reactor experimental loop for irradiation of fuel elements and construction materials, which will be placed in the central experimental channel VK-5. [Serbo-Croat] Ovaj izvestaj opisuje organizacionu semu tehnoloske sluzbe i zadatke koje ona obavlja: rutinska kontrola reaktorsko-fizickih parametara reaktora i saradnja sa korisnicima reaktora, razvojni rad na metodologiji kontrole reaktora i njegovog koriscenja, kontrola rezima rada teskovodnog i gasnog sistema, dozimetrija i tehnicka zastita od zracenja u zgradi reaktora, dekontaminacija i akcidentalna analiza. Posebno poglavlje opisuje izgradnju eksperimentale petlje za ozracivanje gorivnih elemenata i konstrukcionih materijala koja ce biti postavljena u centralnom eksperimentalnom kanalu VK-5 reaktora RA, koja je projektovana kao slozena eksperimentalna instalacija.

RA Research reactor, Part 1, Operation and maintenance of the RA nuclear reactor for 1988; Istrazivacki nuklearni reaktor RA, deo 1, pogon i odrzavanje nukleanog reaktora RA u 1988. godini

Energy Technology Data Exchange (ETDEWEB)

Sotic, O; Martinc, R; Cupac, S; Sulem, B; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1988-12-15

According to the action plan for 1988, operation of the RA reactor should have been restarted in October, but the operating license was not obtained. Control and maintenance of the reactor components was done regularly and efficiently dependent on the availability of the spare parts. The major difficulty was maintenance of the reactor instrumentation. Period of the reactor shutdown was used for repair of the heavy water pumps in the primary coolant loop. With the aim to ensure future safe and reliable reactor operation, action were started concerning renewal of the reactor instrumentation. Design project was done by the soviet company Atomenergoeksport. The contract for constructing this equipment was signed, and it is planned that the equipment will be delivered by the end of 1990. In order to increase the space for storage of the irradiated fuel elements and its more efficient usage, projects were started concerned with reconstruction of the existing fuel handling equipment, increase of the storage space and purification of the water in the fuel storage pools. These projects are scheduled to be finished in mid 1989. This report includes 8 annexes concerning reactor operation, activities of services and financial issues. [Serbo-Croat] Prema planu za 1988. godinu, reaktor RA je trebalo da pusten u rad oktobra meseca, medjutim nije dobio dozvolu za nastavak rada. Kontrola i odrzavanje opreme izvrsavani su redovno i efikasno, u granicama koje su diktirane raspolozivoscu repromaterijala i rezervnih delova. Najvecu poteskocu pricinjavalo je odrzavanje instrumentacije. Period stajanja u 1988. godini iskoriscen je za remont teskovodnih pumpi u primarnom kolu hladjenja. U cilju povecanja pouzdanosti rada reaktora zapoceti su radovi na modernizaciji instrumentacije, projekat je izradjen u sovjetskoj organizaciji Atomenergoeksport, sklopljen je ugovor o izradi ove opreme koja bi trebalo da bude isporucena do kraja 1990. U cilju povecanja prostora za skladistenje ozracenog

Measurement of the effective resonance integral of natural uranium; Merenje efektivnog rezonantnog integrala prirodnog urana

Energy Technology Data Exchange (ETDEWEB)

Markovic, V; Kocic, A [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

1965-12-15

Good understanding of the nuclear properties of the materials in the reactor core is essential for reactor operation. One of the fundamental properties is the resonance absorption of the fuel, which is directly included in the reactor calculation through resonance escape probability and influences the choice of the materials quality in the core. This paper describes the measurement of resonance absorption integral of the natural uranium as a function of the S/M ratio. Improved experiment planning and analysis of results, as well as improvement of the ROB-1 reactor oscillator device related to the interpretation of results and decrease of reactor drift variations during measurement enabled higher precision of results compared to previous experiments. Poznavanje osobina nuklearnih karakteristika materijala koji ulaze u jezgro nuklearnog reaktora predstavlja bitan faktor u njegovom rezimu rada. Jedna od osnovnih je svakako rezonantna apsorpcija goriva, cija velicina - preko faktora rezonantnog izbegavanja - direktno ulazi u proracun nuklearnih reaktora i utice na izbor kvaliteta materijala koji ga sacinjavaju. U radu se opisuje merenje rezonantnog apsorpcionog integrala prirodnog urana u funkciji odnosa S/M. Bolja postavka eksperimenta i interpretacija rezultata, s jedne strane, i poboljsanje uredjaja reaktorskog oscilatora ROB-1 /1/ u pogledu analize podataka i smanjenja promene drifta reaktora u toku merenja, s druge strane, daju znacaj ovom radu u pogledu dobijanja preciznijih rezultata u odnosu na ranije /2/ (author)

I-1 General; I-1 Opsti deo

Energy Technology Data Exchange (ETDEWEB)

NONE

1960-07-01

General part of the regulations and instructions for operation of the RA reactor includes fundamental data about the reactor properties, biological shields, purpose of reactor operation, organizational scheme, rights and responsibilities of the head of laboratory, leaders of the working teams and all the staff of the laboratory for RA reactor exploitation. Opsti deo knjige propisa i uputstva za rad reaktora sadrzi osnovne podatke o reaktoru, biloskoj zastiti, nameni reaktora, prava i duznosti nacelnika, sefova smena i osoblja laboratorije za eksploataciju reaktora RA.

Regulations and instructions; Propisi i uputstva

Energy Technology Data Exchange (ETDEWEB)

NONE

1960-07-01

Regulations and instructions for operating the RA reactor consist of the following chapters: general regulations with the fundamental RA reactor characteristics, operating regulations and instructions for the personnel on duty, regulations for accidental conditions, training program for the staff of the Laboratory for reactor operation. Propisi i uputstva za rad reaktora RA sadrze sledeca poglavlja: opsti deo sa kratkim opisom karakteristika reaktora RA, propisi za rad dezurnog osoblja, propisi za slucaj udesa, program obuke osoblja Laboratorije za eksploataciju reaktora RA.

Data concerning operation and application of RA reactor in 1975, Annex 1; Prilog 1 - Podaci o radu i iskoriscenosti reaktora RA u 1975. godini

Energy Technology Data Exchange (ETDEWEB)

Stanic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1976-01-15

RA reactor was operating according to the plan for 1975 adopted in December of the previous year. It was planned for reactor to be operated at nominal power first 10-20 days each month, three following days were reserved for different power levels according to the users' demand. Four fuel exchanges were planned and fulfilled with minor delay. Data concerning planned and real operation, as well as delays from the plan and shorter interruptions are presented in tables of this Annex. It is shown that all the delays and interruptions which amounted to 104 hours were compensated. [Serbo-Croat] Reaktor RA je radio prema planu rada za 1975. godinu, nacinjenom u decembru prethodne godine. Planirano je da reaktor radi neprekidno prvih 10-20 dana u mesecu na nominalnoj snazi, tri sledeca dana je rezervisano za rad na drugim snagama zavisno od potreba korisnuka. Planirane su i 4 izmene goriva. Podaci o planiranom i ostvarenom radu kao i odstupanjima od plana i kracim prekidima u radu reaktora dati su u tabelama ovog priloga. Vidi se da su sva odstupanja i prekidi u ukupnom trajanju od 104 sata u celini nadoknadjeni.

Adverse reactions, psychological factors, and their effect on donor retention in men and women.

Science.gov (United States)

Veldhuizen, Ingrid; Atsma, Femke; van Dongen, Anne; de Kort, Wim

2012-09-01

This study investigates the effect of a vasovagal reaction (VVR) or needle reaction (NR) on the risk of stopping as a blood donor, taking into account variables from the Theory of Planned Behavior (TPB). Is stopping risk solely related to the adverse reaction itself, or do the TPB variables play a role as well? Emphasis is placed on possible sex differences. TPB variables were assessed within 12,051 whole blood donors. Also, donors reported the occurrence of adverse reactions during or after their last donation. Blood bank records were used to determine whether donors stopped donating within the next 2 years. Logistic regression analyses were performed to estimate the effect of self-reported adverse reactions on stopping risk, adjusting for the TPB variables. Analyses were performed separately for both sexes. Men have a lower odds of reporting a NR or a VVR than women (odds ratio [OR] 0.34, 95% confidence interval [CI], 0.28-0.43; and OR 0.26, 95% CI 0.19-0.36, for NR and VVR, respectively). For both sexes, only a VVR was associated with stopping risk, which is higher in men (men, OR 3.95, 95% CI 2.19-7.11; women, OR 1.78, 95% CI 1.35-2.35). After adjusting for the TPB variables both ORs declined (men, OR 3.38, 95% CI 1.86-6.15; women, OR 1.58, 95% CI 1.17-2.14). Also, self-efficacy and affective attitude are negatively associated with adverse reactions. Female donors report more VVRs than male donors, but male donors have a higher stopping risk after a VVR than female donors. Coping differences and possible reporting tendencies might play a role. For donor retention purposes, prevention and coping techniques should take sex differences into account. © 2012 American Association of Blood Banks.

Ra reactor operation plan for 1976 - Annex 6; Prilog 6 - Plan rada reaktora RA za 1976. godinu

Energy Technology Data Exchange (ETDEWEB)

Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1976-01-15

Contrary to previous years the RA reactor operation plan for 1976 is conditioned by more uncertainties than ever for the following reasons. It is planned for February to repair the components in order to eliminate the consequences of leaking from the vertical experimental channel VK-4 which happened in december 1975. Apart from this, measurements related to transfer of the core to highly enriched fuel under minimum power are foreseen to be performed in February. In April, it would be indispensable to locate the point of He gas leaking and its prevention. Core transfer to highly enriched fuel is planned for April for testing of the fuel elements under operating conditions and step by step increase of the power density up to the nominal power. Complete plan for core transfer would be available by the end of February 1976. It is planned to make-up for the mentioned delays from May-December 1976. [Serbo-Croat] Za razliku od prethodnih godina izrada plana rada reaktora RA za 1976. godinu vezana je za mnogo vise neizvesnosti nego ikada ranije iz sledecih razloga. U februaru se vrsi remont opreme i uklanjanja posledica procurivanja vertikalnog eksperimentalog kanala VK-4, koje se dogodilo decembra 1975. Sem toga u februaru se vrse merenja na minimalnim snagama u sklopu priprema za prelazak na novo gorivo. U aprilu ce biti neophodno lociranje mesta gde istice He gas kao i otklanjanje uzroka ovog curenja. Planirano je da se u aprilu ubaci novo gorivo u jezgro u cilju testiranja pod radnim uslovima uz postepeno povecanje snage do nominalne. Planirano je da se smanjeni obim rada usled navedenih uslova nadoknadi u potpunosti u periodu maj-decembar 1976.

Dispersion fuel for nuclear research facilities

International Nuclear Information System (INIS)

Kushtym, A.V.; Belash, M.M.; Zigunov, V.V.; Slabospitska, O.O.; Zuyok, V.A.

2017-01-01

Designs and process flow sheets for production of nuclear fuel rod elements and assemblies TVS-XD with dispersion composition UO_2+Al are presented. The results of fuel rod thermal calculation applied to Kharkiv subcritical assembly and Kyiv research reactor VVR-M, comparative characteristics of these fuel elements, the results of metallographic analyses and corrosion tests of fuel pellets are given in this paper

The polarized neutron reflectometer 'Reverans'

Energy Technology Data Exchange (ETDEWEB)

Radzhabov, A.K. [Petersburg Nuclear Physics Institute, Gatchina, St. Petersburg 188300 (Russian Federation)]. E-mail: akr@pnpi.spb.ru; Gordeev, G.P. [Petersburg Nuclear Physics Institute, Gatchina, St. Petersburg 188300 (Russian Federation); Lazebnik, I.M. [Petersburg Nuclear Physics Institute, Gatchina, St. Petersburg 188300 (Russian Federation); Axelrod, L.A. [Petersburg Nuclear Physics Institute, Gatchina, St. Petersburg 188300 (Russian Federation); Zabenkin, V.N. [Petersburg Nuclear Physics Institute, Gatchina, St. Petersburg 188300 (Russian Federation)

2007-07-15

The polarized neutron reflectometer 'Reverans' with a vertical plane of scattering is being installed at the VVR-M reactor (Gatchina, Russia). It will be used for research on phase boundaries, interfaces and free surfaces. Systems under study can be both magnetic and nonmagnetic ones. At present the installation of the reflectometer is at the final stage. The parameters and abilities of the reflectometer are presented.

Research nuclear reactor RA - Annual Report 1975. Operation and maintenance; Istrazivacki nuklearni reaktor RA - Izvestaj za 1975. godinu - Pogon i odrzavanje

Energy Technology Data Exchange (ETDEWEB)

Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1976-01-15

The plan for 1975 was successfully fulfilled. This is reflected in research related to improvement of operating properties of the RA reactor, mostly due to the effort of the RA staff employed in operation and maintenance of the reactor. Fuel saving achieved by this activity amounted to about 38% (80% enriched fuel). Preliminary work is done, concerned with new reactor core with highly enriched fuel. This is a significant saving as well. New fuel elements have arrived at the end of this year. It is going to enable increase of neutron flux by 50% without changing the nominal operating power. The possibility of further improvement of the reactor are analyzed, to enable material testing and production of radioactive sources. Mid term plan for reactor operation was made according to this analysis. It is planned to further increase the neutron flux in isolated smaller zones, and building new experimental loops with cooling and fast neutron converters. Much was done to increase the safety level of reactor operation and preparing the safety report. [Serbo-Croat] Izvrsenje zadataka u 1975. godini bilo je uspesno. To se ogleda u povecanju istrazivackog rada vezanog za poboljsanje eksploatacionih karakteristika reaktora RA, pretezno koriscenjem sopstvenog kadra angazovanog u pogonu i odrzavanju reaktora. Ovim radom postignuta je usteda goriva od oko 38% (80% obogaceno gorivo). Izvrseni su preliminarni radovi na prevodjenju reaktora RA na novo gorivo, sto je takodje velika usteda. Novo gorivo je stiglo krajem godine i ono ce obezbediti porast neutronskog fluksa od 50%, bez promene nominalne snage reaktora. Izvrsena je analiza mogucnosti daljeg usavrsavanja reaktora za potrebe ispitivanja materijala kao i proizvodnju radioaktivnih izvora. Na osnovu ove analize nacinjen je srednjorocni program rada reaktora RA sa tezistem na daljem povecanju fluksa u izdvojenim manjim zonama i ugradnju 'hladjenih petlji' i brzih konvertora. Mnogo je ucinjeno na povecanju stepena sigurnosti

Variational variance reduction for particle transport eigenvalue calculations using Monte Carlo adjoint simulation

International Nuclear Information System (INIS)

Densmore, Jeffery D.; Larsen, Edward W.

2003-01-01

The Variational Variance Reduction (VVR) method is an effective technique for increasing the efficiency of Monte Carlo simulations [Ann. Nucl. Energy 28 (2001) 457; Nucl. Sci. Eng., in press]. This method uses a variational functional, which employs first-order estimates of forward and adjoint fluxes, to yield a second-order estimate of a desired system characteristic - which, in this paper, is the criticality eigenvalue k. If Monte Carlo estimates of the forward and adjoint fluxes are used, each having global 'first-order' errors of O(1/√N), where N is the number of histories used in the Monte Carlo simulation, then the statistical error in the VVR estimation of k will in principle be O(1/N). In this paper, we develop this theoretical possibility and demonstrate with numerical examples that implementations of the VVR method for criticality problems can approximate O(1/N) convergence for significantly large values of N

Dosimetry and technical radiation protection at the RA in 1974; Dozimetrija i tehnicka zastita od zracenja kod reaktora RA u 1974. godini

Energy Technology Data Exchange (ETDEWEB)

Ninkovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1975-01-15

This report include the analysis of the dosimetry and technical radiation protection results collected during 1974. The first part shows the data about the fundamental exposure to radiation and the statistical review of the total number of measurements. The following are included as well: measured values of radioactive gases and aerosol contents in air; contamination level of surfaces, clothes and uncovered parts of the staff bodies. Analysis of the personnel exposure is presented in the second part of the report. It was stated that the maximum individual external dose was 2.13R, and the exposure dose was 1/5 lower than of the annual dose limit for 90% of the exposed personnel. It was estimated that that the internal contamination is negligible compared to the external contamination. This statement was based on the frequency of tasks in the contaminated zones, undertaken control and protection measures, as well as on the evaluation of the expected internal contamination. Comparative evaluation of the occupational exposures is given for the past five years. This showed that the exposure in 1974 was lower than during previous years. The third part of the report covers the numerical data about the quantity of the collected radioactive waste, total size of contaminated and decontaminated surfaces and number of decontaminated objects. A brief analysis of the accidents occurred during this year under regular reactor operating conditions, maintenance and repair is given at the end. It was stated that there has been no accident that would cause exposure higher than the prescribed limits or any significant contamination of the working space or environment. Maximum individual dose was 1.4 R, and contamination of the uncovered parts of the bodies was about 6 MDNK (maximum permissible contamination level) [Serbo-Croat] U ovom radu prikazani su rezultati sakupljeni u toku godine u okviru dozimetrijske kontrole i tehnicke zastite kod reaktora. U prvom delu rada izlozeni su

Radiation protection at the RA reactor in 1987, Part I: Control of the working environment - dosimetry and radiation protection at the RA reactor, Annex 1; Prilog 1, Zastita od zracenja kod reaktora RA u 1987. godini - Deo 1: Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Ninkovic, M; Bjelanovic, J; Minincic, Z; Komatina, R; Raicevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Laboratory for radiation and environmental proetecion, Beograd (Serbia and Montenegro)

1987-12-15

This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted was less than 6.0 mSv during past 10 months. Individual exposures for 9/10 of the personnel were less than 1/10 of the annual permissible exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. During 1987 there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radiacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila 6,0 mSv, a da su pojadinacna izlaganja vise od 9/10 radnog osoblja bila manja od 1/10 godisnje granicne vrednosti. Dati su takodje uporedni podaci o ozracivanju osoblja u prethodnoj, kao i u pet proteklih godina, iz kojih

RA Reactor; Reaktor RA

Energy Technology Data Exchange (ETDEWEB)

NONE

1978-02-15

In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation. [Serbo-Croat] Pored osnovnih karakeristika reaktora RA, organizacije rada i finansijskih pokazatelja, razmatra se stanje opreme reaktora nakon 18 godina rada, pitanja dozvole za rad sa 80% obogacenim gorivom, problem skladistenja isluzenog goriva u bazenu zgrade reaktora i potreba za obnavljanjem komponenti opreme, pre svega elektronske.

Research nuclear reactor RA - Annual report 1992; Istrazivacki nuklearni reaktor RA - Izvestaj za 1992. godinu

Energy Technology Data Exchange (ETDEWEB)

Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1992-12-01

Research reactor RA Annual report for year 1992 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. First part includes 8 annexes describing reactor operation, activities of services for maintenance of reactor components and instrumentation, financial report and staffing. Second annex B is a paper by Z. Vukadin 'Recurrence formulas for evaluating expansion series of depletion functions' published in 'Kerntechnik' 56, (1991) No.6 (INIS record no. 23024136. Second part of the report is devoted to radiation protection issues and contains 4 annexes with data about radiation control of the working environment and reactor environment, description of decontamination activities, collection of radioactive wastes, and meteorology data. [Serbo-Croat] Godisnji izvestaj o radu nuklearnog reaktora RA za 1992. godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA. Prvi deo sadrzi 8 priloga, koji opisuju rad reaktora i poslove sluzbi za odrzavanje opreme i komponenti, finansijski izvestaj, kadrovsku strukturu osoblja reaktora. Drugi prilog (B) je rad Z. Vukadina 'Recurrence formulas for evaluating expansion series of depletion functions' objavljen u casopisu Kerntechnik, 1991. Drugi deo izvestaja o poslovima zastite od zracenja sadrzi 4 priloga sa podacima radijacione kontrole radne sredine i okoline reaktora, opis poslova dekontaminacije i sakupljanja radioaktivnih materija, kao i meteoroloske podatke.

Reproduction of the RA reactor fuel element fabrication; Reprodukcija izrade gorivnog elementa za reaktor RA

Energy Technology Data Exchange (ETDEWEB)

Novakovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1961-12-15

This document includes the following nine reports: Final report on task 08/12 - testing the Ra reactor fuel element; design concept for fabrication of RA reactor fuel element; investigation of the microstructure of the Ra reactor fuel element; Final report on task 08/13 producing binary alloys with Al, Mo, Zr, Nb and B additions; fabrication of U-Al alloy; final report on tasks 08/14 and 08/16; final report on task 08/32 diffusion bond between the fuel and the cladding of the Ra reactor fuel element; Final report on task 08/33, fabrication of the RA reactor fuel element cladding; and final report on task 08/36, diffusion of solid state metals. Ovaj rad sadrzi devet priloga: 1. Zavrsni izvestaj o podzadatku 08/12, ispitivanje elementa goriva reaktora RA; 2. Koncepcija izrade gorivnog elementa reaktora RA; 3. Ispitivanje mikrostrukture gorivnog elementa reaktora RA; 4. Zavrsni izvestaj o podzadatku 08/13, dobijanje binarnih legura urana sa legirajucim komponentama Al, Mo, Zr, Nb i B; 5. Dobijanje legure U-Al; 6. Zavrsni izvestaj o podzadacima 08/14 i 08/16; 7. Zavrsni izvestaj o podzadatku 08/32, difuziona veza goriva i kosuljice gorivnog elementa reaktora RA; 8. Zavrsni izvestaj o podzadatku 08/33, izrada kosuljice gorivnog elementa reaktora RA; 9. Zavrsni izvestaj o podzadatku 08/36, difuzija kod metala u cvrstom stanju.

Variational Variance Reduction for Monte Carlo Criticality Calculations

International Nuclear Information System (INIS)

Densmore, Jeffery D.; Larsen, Edward W.

2001-01-01

A new variational variance reduction (VVR) method for Monte Carlo criticality calculations was developed. This method employs (a) a variational functional that is more accurate than the standard direct functional, (b) a representation of the deterministically obtained adjoint flux that is especially accurate for optically thick problems with high scattering ratios, and (c) estimates of the forward flux obtained by Monte Carlo. The VVR method requires no nonanalog Monte Carlo biasing, but it may be used in conjunction with Monte Carlo biasing schemes. Some results are presented from a class of criticality calculations involving alternating arrays of fuel and moderator regions

Performance Characteristics of the Experimental Boiling Water Reactor from 0 to 100 MW(t); Performances de l'EBWR de 0 a 100 MW; Rabochaya kharakteristika ehksperimental'nogo kipyashchego reaktora EBWR pri moshchnosti 0 - 100 mgvt.; Rendimiento del reactor experimental de agua hirviente (EBWR) entre 0 y 100 MW

Energy Technology Data Exchange (ETDEWEB)

Iskenderian, A.; Lipinski, W. C.; Petrick, M.; Wimunc, E. A. [Argonne National Laboratory, Argonne, IL (United States)

1963-10-15

.d. Rabochaya kharakteristika reaktora EBWR opredelyalas' pochti isklyuchitel'no po vydeleniyu para v osadok v spusknoj trube, po unosu zhidkosti ehfluentom para i kosvenno, putem lokalizatsii dejstvitel'noj poverkhnosti razdela v korpuse reaktora. Vydelenie para v osadok bylo dominiruyushchim faktorom v diapazone bolee nizkikh ehnergij. Pri moshchnosti svyshe 65 mgvt rabochaya kharakteristika reaktora rezko menyalas'. Skorost' otdeleniya para dostigla 33 sm/sek i vysota parovogo prostranstva umen'shilas' do 1 m. Pri takikh usloviyakh proiskhodil unos zhidkosti, kotoryj bystro uvelichivalsya s uvelicheniem moshchnosti. Reaktor bol'she ne vel sebya kak kipyashchij reaktor s pryamym tsiklom; v nekotorom rode on vel sebya kak reaktor s dvojnym tsiklom estestvennoj tsirkulyatsii. (author)

Determination of the tritium content in the reactor heavy water, Phase II; Odredjivanje porasta kolicine tritijuma u reaktorskoj teskoj vodi, II faza

Energy Technology Data Exchange (ETDEWEB)

Ribnikar, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1963-07-15

Measurement results of the {sup 3}H activity in non-irradiated water and after reactor operation are presented. Methods were developed for sampling and radiochemical water purification by ion exchange and multiple distillation. Methods for absolute measurement of soft beta radiation of tritium were established. Migration of tritium through the heavy water RA reactor system was monitored. Results were compared with other measured reactor parameters. Prikazani su rezultati merenja aktivnosti {sup 3}H u nezracenoj vodi i posle rada reaktora; razradjeni su metodi za uzimanje i radiohemijsko preciscavanje vode putem jonske izmene i visestepene destilacije; postavljeni metodi za apsolutno merenje mekog beta-zracenja tritijuma; pracene su migracije tritijuma kroz teskovodni sistem reaktora; takodje su interpretirani i poredjeni rezultati sa drugim merenim parametrima reaktora.

Detection of tritium in the air surrounding the heavy water reactors; Elementi detekcije tricijuma u vazduhu kod teskovodnih nuklearnih reaktora

Energy Technology Data Exchange (ETDEWEB)

Ninkovic, M; Matic-Vukmirovic, Z; Hadzisehovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1967-03-15

This paper contains the study of the literature concerned with physical properties of the tritium, problems of detection control of the tritium level in the atmosphere in the vicinity of heavy water reactors. It is stated that a complete and efficient control of tritium activity, from radiation protection point of view can be achieved only by simultaneous triple measurements: direct measurement of tritium in the air by stationary or movable instruments; air sampling and measurement of activity by laboratory instrumentation; and measurement of tritium in the bio-material of the personnel who have inhaled air contaminated with tritium. Laboratory equipment was adapted for tritium detection in air samples. A method for measuring the specific tritium activity was developed and implemented. The tritium level and distribution in the air were measured during exchange of the fuel channel in the RA reactor. The obtained results indicate that tritium could be dangerous for the staff involved. Proucena je literatura u kojoj se tretiraju osnovne fizicke karakteristike tricijuma, kao i problemi detekcije i kontrole u vazduhu kod teskovodnih nuklearnih reaktora. Utvrdjeno je da kompletna i efikasna kontrola aktivnosti tricijuma, sa aspekta zastite od zracenja, moze biti ostvarena samo ako se vrse istovremeno trostruka merenja: merenje aktivnosti tricijuma u vazduhu direktno, prenosnim ili stacioniranim instrumentima; uzimanje uzoraka vazduha i merenje aktivnosti na laboratorijskoj aparaturi; i merenje aktivnosti tricijuma u biomaterijalu osoblja koje je udisalo vazduh kontaminiran tricijumom. Izvrsena je adaptacija laboratorijske aparature za potrebe detekcije tricijuma u uzorcima vazduha. Razradjen je i uhodan postupak merenja koncentracije aktivnosti tricijuma u uzorcima vazduha. Izvrsena su merenja i dobijeni su rezultati o nivou i raspodeli tricijuma u vazduhu pri operaciji zamene kanala sa gorivom na reaktoru RA u Vinci. Dobijeni rezultati ukazuju na opasnost koju po radno

Safety report for the independent CO{sub 2} loop for cooling the samples irradiated in the vertical experimental channels of the RA reactor; Izvestaj o sigurnosti za nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracenih u vertikalnim eksperimentalnim kanalima reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Pavlovic, A; Zivkovic, S; Milosevic, M; Strugar, P [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1969-07-01

Independent CO{sub 2} loop was designed for cooling the samples irradiated in the vertical experimental channels in the region of heavy water or in the graphite reflector. It is considered as a significant improvement of the RA reactor experimental possibilities. Six 'heads' are placed in vertical experimental channels and connected in parallel with the outer loop which contains out-of-reactor equipment. It is planned to irradiate samples in the 'heads' of the loop for the needs of Hot laboratory and Laboratory for reactor materials. Heat generated during sample irradiation is removed by CO{sub 2} circulation. This report contains detailed description of the main loop, auxiliary systems, calculation results of anti reactivity and activation of construction materials of the low-temperature CO{sub 2} loop. A separate chapter is devoted to control and regulation of temperature and pressure. Testing of the fundamental parameters of the coolant loop showed that it could fulfill more demanding tasks than designed by the project. Annex of this report includes results of leak testing for the loop 'heads' in vertical experimental channels VEK-6 and VEK-8 by helium leak detector. [Serbo-Croat] Nezavisno kolo CO{sub 2} namenjeno je za hladjenje uzoraka ozracivanih u VEK reaktora u zoni teske vode i u zoni grafita, i predstavlja znacajan doprinos povecanju eksperimentalnih mogucnosti reaktora RA. Sest 'glava' je postavljeno u vertikalne eksperimentalne kanale i paralelno vezano na spoljno kolo koje sadrzi vanreaktorsku opremu. U glavama petlje se predvidja ozracivanje raznovrsnih uzoraka materijala za potrebe Laboratorije za visoku aktivnost i Laboratorije za reaktorske materijale. Toplota koja se generise prilikom ozracivanja uzoraka odvodi se cirkulacijom CO{sub 2}. Ovaj izvestaj sadrzi detaljan opis: glavnog kola, pomocnih sistema; rezultate proracuna antireaktivnosti i aktivacije konstrukcionih elemenata glave niskotemperaturne petlje CO{sub 2}. Posebno poglavlje posveceno

Design project of the dosimetry control system in the independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels, Vol. V; Album V: Predprojekat sistema dozimetrijske kontrole u nezavisnom kolu CO{sub 2} za hladjenje uzoraka ozracivanih u VEK reaktora RA

Energy Technology Data Exchange (ETDEWEB)

NONE

1964-07-01

Design project of the dosimetry control system in the independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels includes the following: calculations of CO{sub 2} gas activity, design of the dosimetry control system, review of the changes that should be done in the RA reactor building for installing the independent CO{sub 2} loop, specification of the materials with cost estimation, engineering drawings of the system. Predprojekat sistema dozimetrijske kontrole u nezavisnom kolu CO{sub 2} za hladjenje uzoraka ozracivanih u vertikalnim eksperimentalnim kanalima reaktora RA sadrzi: proracun aktivnosti gasa CO{sub 2}, idejno resenje sistema dozimetrijske kontrole, pregled izmena koje bi trebalo izvrsiti u zgradi RA u vezi montaze nezavisnog kola CO{sub 2}, specifikaciju materijala sa cenom kostanja i graficku dokumentaciju predprojekta.

II-1 General regulatory guide for staff on duty; II-1 Opsti pravilnik za rad dezurnog osoblja

Energy Technology Data Exchange (ETDEWEB)

NONE

1960-07-01

Personnel responsible for RA reactor operation is working in shifts. This regulatory guide describes in detail rights, tasks and responsibilities of each staff member in duty when operating the reactor under regular conditions, during start-up, during shutdown, during repair and maintenance shutdown periods. Rad reaktora odvija se po smenama. Ovaj pravilnik regulise prava, duznosti i odgovornost svakog od clanova tima u smeni pojedinacno u regularnim uslovima rada, prilikom remonta, u toku stajanja, dostizanja nominalne snage, zaustavljanja rada reaktora.

Dosimetry and radiation protection at the RA reactor in 1972; Dozimetrija i zastita kod reaktora RA u 1972. godini

Energy Technology Data Exchange (ETDEWEB)

Ninkovic, M M [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

1973-07-01

Dosimetry results collected within radiation protection of the RA reactor during this year are presented. Neutron and gamma radiation data were measured at characteristic control points. Statistical review of the total number of measurement is given as well. The report includes contents of radioactive gasses and aerosols in the air, as well as the contamination data of surfaces, clothes and uncovered body parts of the personnel. Particular accident which occurred during dismantling of the experimental channel containing the capsule with the new fuel element was analysed. This accident occurred at the RA reactor at the beginning of this year. It was found that that the maximum individual external dose was 2.2 R, and that only one individual was exposed to this dose. About 15% of the personnel was exposed to doses between 1 and 2 R, the remaining 85% was exposed to doses less than 1 R. Base on the frequency of activities undertaken in the contaminated regions, safety and control measures and expected internal exposure of the personnel, it was evaluated that the internal exposure could be neglected compared to the external exposure of the personnel. Prikazani su rezultati sakupljani u toku godine u okviru dozimetrijske kontrole i zastite kod reaktora. Dati su podaci o nivoima neutrona i gama zracenja na karakteristicnim kontrolnim mestima, kao i statisticki pregledi ukupnog broja merenja. Navedeni su rezultati merenja sadrzaja radioaktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela radnog osoblja. Analiziran je specifican akcident koji se odigrao na reaktoru pocetkom godine, pri demontazi eksperimentalnog kanala sa kapsulom novog gorivog elementa. Na kraju, izlozena je analiza ozracivanja radnog osoblja. Konstatovano je da je maksimalna individualna doza spoljasnjeg ozracivanja bila 2,2 (R), i da je ovoj dozi bilo izlozeno samo jedno lice. Oko 15% osoblja bilo je izlozeno dozama izmedju 1 i 2 (R), a ostalih 85

Decision, Annex 3[Organizational structure of the Division for reactor maintenance]; Prilog br. 3, Odluka

Energy Technology Data Exchange (ETDEWEB)

Pavicevic, M [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1965-12-15

The objective of the decision about the change in the organizational scheme of the Division for RA reactor maintenance is to achieve efficiency. The tasks are precisely defined as to divide the maintenance and repair tasks from special ones related to improvement of reactor operation its applicability. [Serbo-Croat] U cilju poboljsanja organizacije rada Odelenja odrzavanja reaktora RA, kao i efikasnijeg koriscenja raspolozivog kadra izvrsice se razgranicenje poslova odrzavanja i remonta od posebnih zadataka koji se odnose na poboljsanje rada reaktora i povecanje njegovih mogucnosti.

Annual report of the maintenance division for 1965; Godisnji izvestaj Odelenja odrzavanja za 1965. g

Energy Technology Data Exchange (ETDEWEB)

Nikolic, M [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1965-12-15

The personnel of the Division is organized in groups, each responsible for a number of tasks related to maintenance of reactor mechanical structures, electric equipment, electronic equipment. According to the action plan for 1965 the division for RA reactor maintenance the main activities were: planned maintenance of the reactor components, planned repair of the main components, indispensable repairs during reactor operation, repair during planned shutdown periods and tasks related to improvement of operation components and systems. Quite a significant number of failures was related to electronic equipment resulting from failures of thermometers in the heavy water system due to vibrations of the pumps. A number of spare parts and tools were produced needed for maintenance of reactor components, as well as instruments for control and calibration of reactor measuring devices. [Serbo-Croat] Odelenje odrzavanja reaktora RA organizovano je po grupama, od kojih je svaka odgovorna za odrzavanje pojedinih delova sistema: masinske opreme, elektricne opreme, elektronskih uredjaja. Prema planu rada za 1965. godinu Odelenja za odrzavanje reaktora RA osnovne aktivnosti bile su: planirano odrzavanje komponenti reaktora, planirane popravke osnovnih komponenti, neodlozne popravke tokom eksploatacije i u toku planiranih zaustavljanja kao i usavrsavanje opreme i sistema. Znatan broj kvarova pojavio se na elektronskoj opremi usled kvarova termometara u sistemu teske vode usled vibracija koje izazivaju pumpe. Odredjeni broj delova izradjen je za potrebe odrzavanja komponenti reaktora, kao i instrumenata za kontrolu i kalibraciju mernih uredjaja.

RA reactor operation and maintenance in 1989, Part 1; Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1989. godini

Energy Technology Data Exchange (ETDEWEB)

Sotic, O; Martinc, R; Cupac, S; Sulem, B; Zivotic, Z; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1989-12-15

, koja je zavrsena 1989, i izradu uredjaja za rukovanje ozracenim gorivom, koji je u fazi montiranja. Planirano je da ovi poslovi budu zavrseni do sredine 1990. godine. Obuka postojeceg osoblja sprovodi se redovno ali novoprimljeni radnici obuceni za rad u pogonu nisu mogli da steknu potrebno sikustvo posto reaktor nije bio u pogonu od 1984. Nedostatak sredstava onemogucava prijem novih radnika i utice na celokupni status i aktivnosti vezane za rekonsrukciju i modernizaciju reaktora RA.

Action plan for 1965, Annex 2; Prilog br. 2 - Plan zadataka u 1965. godini

Energy Technology Data Exchange (ETDEWEB)

NONE

1965-12-15

Action plan presented in this annex includes tasks of the mechanics, electrical and electronic equipment services. It includes a detailed list of planned and preventive maintenance actions related to the heavy water system, technical water system, helium system, reactor core, transportation equipment, hot cells, heating and ventilation systems in the reactor building, power supply system, auxiliary systems in the RA reactor building. [Serbo-Croat] Plan zadataka obuhvata aktivnosti masinske i elektro grupe na preventivnom odrzavanju i planskom remontu sistema teske vode, sistema tehnicke vode, sistema helijuma, centralnog tela reaktora, sistema grejanja i ventilacije, sistema za snabdevanje elektricnom energijom, i ostalih pomocnih sistema u zgradi reaktora RA.

Effect of neutron irradiation on vitreous carbon

International Nuclear Information System (INIS)

Kurolenkin, E.I.; Virgil'ev, Yu.S.; Chugunova, T.K.

1989-01-01

The change in mass (m), volume (V), specific electric resistance (ρ), coefficient of linear thermal expansion (α), dynamic elasticity modulus (E), and limit of bending strength (σ) of vitreous carbon are studied upon neutron irradiation. Samples for study were two forms of vitreous carbon obtained by hardening thermally reactive polymers at 900-1,000 degree K. Phenol-formaldehyde (bakelite lacquer A, Bakelite A) and furfural-phenol-formaldehyde (FM-2) resin were used. They were irradiated in the experimental water - water VVR-M reactor between 360-1,030 degree K. The maximal neutron flux was 1.65·10 21 neut/cm 2 . Neutron irradiation of vitreous carbon led to its shrinkage and accompanied weakening. Shrinkage and weakening of vitreous carbon was decreased with an increase of treatment and irradiation temperatures

Radiation protection at the RA Reactor in 1986, Part -2, Annex 1, Radioactivity control of working environment, dosimetry; Deo 2 - Prilog 1 - Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Ninkovic, M; Bjelanovic, J; Minincic, Z; Komatina, R; Raicevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1986-12-01

This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted to 20.5 mSV during past 10 months. Individual exposures for 7/10 of the personnel were less than 1/10 of the annual permissible exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. The last part analyzes accidents occurred at the reactor during 1986. It was found that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radiacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila 20,5 mSv, a da su pojadinacna izlaganja vise od 7/10 radnog osoblja bila manja od 1/10 godisnje granicne vrednosti. Dati su takodje uporedni podaci o

Radiation protection at the RA Reactor in 1988, Part -2, Annex 1, Radioactivity control of working environment, dosimetry; Deo 2 - Prilog 1 - Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Ninkovic, M; Bjelanovic, J; Minincic, Z; Glodic, S; Raicevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1988-12-15

This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted was less than 0.5 mSv during past 10 months. Individual exposures for 9/10 of the personnel were less than 1/10 of the annual permissible exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. During 1988 there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radijacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila 0,5 mSv, a da su pojedinacna izlaganja vise od 9/10 radnog osoblja bila manja od 1/10 godisnje granicne vrednosti. Dati su takodje uporedni podaci o ozracivanju osoblja u prethodnoj, kao i u pet proteklih godina, iz

Adverse reactions, psychological factors, and their effect on donor retention in men and women

NARCIS (Netherlands)

Veldhuizen, I.J.T.; Atsma, F.; van Dongen, A.; de Kort, W.

2012-01-01

BACKGROUND: This study investigates the effect of a vasovagal reaction (VVR) or needle reaction (NR) on the risk of stopping as a blood donor, taking into account variables from the Theory of Planned Behavior (TPB). Is stopping risk solely related to the adverse reaction itself, or do the TPB

Use of Endophytic and Rhizosphere Actinobacteria from Grapevine Plants To Reduce Nursery Fungal Graft Infections That Lead to Young Grapevine Decline.

Science.gov (United States)

Álvarez-Pérez, José Manuel; González-García, Sandra; Cobos, Rebeca; Olego, Miguel Ángel; Ibañez, Ana; Díez-Galán, Alba; Garzón-Jimeno, Enrique; Coque, Juan José R

2017-12-15

Endophytic and rhizosphere actinobacteria isolated from the root system of 1-year-old grafted Vitis vinifera plants were evaluated for their activities against fungi that cause grapevine trunk diseases. A total of 58 endophytic and 94 rhizosphere isolates were tested. Based on an in vitro bioassay, 15.5% of the endophytic isolates and 30.8% of the rhizosphere isolates exhibited antifungal activity against the fungal pathogen Diplodia seriata , whereas 13.8% of the endophytic isolates and 16.0% of the rhizosphere isolates showed antifungal activity against Dactylonectria macrodidyma (formerly Ilyonectria macrodidyma ). The strains which showed the greatest in vitro efficacy against both pathogens were further analyzed for their ability to inhibit the growth of Phaeomoniella chlamydospora and Phaeoacremonium minimum (formerly Phaeoacremonium aleophilum ). Based on their antifungal activity, three rhizosphere isolates and three endophytic isolates were applied on grafts in an open-root field nursery in a 3-year trial. The field trial led to the identification of one endophytic strain, Streptomyces sp. VV/E1, and two rhizosphere isolates, Streptomyces sp. VV/R1 and Streptomyces sp. VV/R4, which significantly reduced the infection rates produced by the fungal pathogens Dactylonectria sp., Ilyonectria sp., P. chlamydospora , and P. minimum , all of which cause young grapevine decline. The VV/R1 and VV/R4 isolates also significantly reduced the mortality level of grafted plants in the nursery. This study shows that certain actinobacteria could represent a promising new tool for controlling fungal trunk pathogens that infect grapevine plants through the root system in nurseries. IMPORTANCE Grapevine trunk diseases are a major threat to the wine and grape industry worldwide. They cause a significant reduction in yields as well as in grape quality, and they can even cause plant death. Trunk diseases are caused by fungal pathogens that enter through pruning wounds and/or the

Establishing the fuel burn-up measuring system for 106 irradiated assemblies of Dalat reactor by using gamma spectrometer method

International Nuclear Information System (INIS)

Nguyen Minh Tuan; Pham Quang Huy; Tran Tri Vien; Trang Cao Su; Tran Quoc Duong; Dang Tran Thai Nguyen

2013-01-01

The fuel burn-up is an important parameter needed to be monitored and determined during a reactor operation and fuel management. The fuel burn-up can be calculated using computer codes and experimentally measured. This work presents the theory and experimental method applied to determine the burn-up of the irradiated and 36% enriched VVR-M2 fuel type assemblies of Dalat reactor. The method is based on measurement of Cs-137 absolute specific activity using gamma spectrometer. Designed measuring system consists of a collimator tube, high purity Germanium detector (HPGe) and associated electronics modules and online computer data acquisition system. The obtained results of measurement are comparable with theoretically calculated results. (author)

In-EDTA as activable tracer in hydrogeological investigations

International Nuclear Information System (INIS)

Stanescu, S.P.; Gaspar, E.; Spiridon, S.; Farcasiu, O.M.; Catilina, R.

1982-12-01

Two experiments are presented, on the possibilities of the use of indium in the form of the In-EDTA complex, as an activable tracer for hydrogeological studies. The determination of indium concentrations in the sampled water has been carried out by using the coprecipitation of indium with bismuth hydroxide, the neutron activation at the VVR-S reactor of the Institute for Nuclear Physics and Engineering - Bucharest and the measurement on the 417.0 keV line of sup(116m)In with the Ge(Li) spectrometric device. The advantages of the utilization of In-EDTA as a tracer for marking large volumes of water and of some long transit waters (of the order of months) have resulted. (authors)

Adverse Reactions in Allogeneic Blood Donors: A Tertiary Care Experience from a Developing Country

Directory of Open Access Journals (Sweden)

Sadia Sultan

2016-03-01

Full Text Available Objectives: Fragmented blood transfusion services along with an unmotivated blood donation culture often leads to blood shortage. Donor retention is crucial to meet the increasing blood demand, and adverse donor reactions have a negative impact on donor return. The aim of this study was to estimate adverse donor reactions and identify any demographic association.   Methods: We conducted a prospective study between January 2011 and December 2013. A total of 41,759 healthy donors were enrolled. Professionally trained donor attendants drew blood and all donors were observed during and following donation for possible adverse events for 20 minutes. Blood donors were asked to report if they suffered from any delayed adverse consequences.   Results: Out of 41,759 blood donors, 537 (1.3% experienced adverse reactions. The incidence was one in every 78 donations. The mean age of donors who experienced adverse events was 26.0±6.8 years, and all were male. Out of 537 donors, 429 (80% developed vasovagal reaction (VVR, 133 (25% had nausea, 63 (12% fainted, 35 (6% developed hyperventilation, 9 (2% had delayed syncope, and 9 (2% developed hematoma. Arterial prick, nerve injury, cardiac arrest, and seizures were not observed. Donors aged less than < 30 years and weighing < 70 kg were significantly associated with VVR, hyperventilation, and nausea (p < 0.005. Undergraduates and Urdu speaking donors also had a significant association with fainting and nausea, respectively (p < 0.05.   Conclusion: The prevalence of adverse events was low at our tertiary center. A VVR was the predominant adverse reaction and was associated with age and weight. Our study highlights the importance of these parameters in the donation process. A well-trained and experienced phlebotomist and pre-evaluation counseling of blood donors could further minimize the adverse reactions.

Planning the Decommissioning of Research Reactors

Energy Technology Data Exchange (ETDEWEB)

Podlaha, J., E-mail: pod@ujv.cz [Nuclear Research Institute Rez, 25068 Rez (Czech Republic)

2013-08-15

In the Czech Republic, three research nuclear reactors are in operation. According to the valid legislation, preliminary decommissioning plans have been prepared for all research reactors in the Czech Republic. The decommissioning plans shall be updated at least every 5 years. Decommissioning funds have been established and financial resources are regularly deposited. Current situation in planning of decommissioning of research reactors in the Czech Republic, especially planning of decommissioning of the LVR-15 research reactor is described in this paper. There appeared new circumstances having wide impact on the decommissioning planning of the LVR-15 research reactor: (1) Shipment of spent fuel to the Russian Federation for reprocessing and (2) preparation of processing of radioactive waste from reconstruction of the VVR-S research reactor (now LVR-15 research reactor). The experience from spent fuel shipment to the Russian Federation and from the process of radiological characterization and processing of radioactive waste from reconstruction of the VVR-S research reactor (now the LVR-15 research reactor) and the impact on the decommissioning planning is described in this paper. (author)

Silicon-lithium nuclear radiation detectors. Kremnii-litievye detektory yadernogo izlucheniya

Energy Technology Data Exchange (ETDEWEB)

Azimov, S.A.; Muminov, R.A.; Shamirzaev, S.Kh.; Yafasov, A.Ya.

1981-01-01

A presentation is made of the physical principles underlying the design, building, and technology of silicon-lithium detectors and ways of improving them. Criteria of nuclear radiation control and selection and the connection between radiation and detector properties are discussed. A study is made of the effect that various defects have on the process of charge collection and formation of amplitude spectra during the recording of various types of particles. A detailed examination is made of the optimal technological systems for making detectors with high energy and time resolutions, and features of producing high-quality detectors which employ the use of ion-laser and other methods of modern semiconductor technology. 322 references, 102 figures, 2 tables.

Evolution of secondary-phase precipitates during annealing of the 12Kh18N9T steel irradiated with neutrons to a dose of 5 DPA

Science.gov (United States)

Tsai, K. V.; Maksimkin, O. P.; Turubarova, L. G.

2007-03-01

The formation and evolution of thermally-induced secondary precipitates in an austenitic stainless steel 12Kh18N9T irradiated in the core of a laboratory reactor VVR-K to a dose of 5 dpa and subjected to post-radiation isochronous annealings for 1 h in a temperature range from 450 to 1050°C have been studied using transmission electron microscopy (TEM) and microhardness measurements. It has been shown that the formation of stitch (secondary) titanium carbides and M 23C6 carbides at grain and twin boundaries after annealing at 1050°C is preceded by a complex evolution of fineparticles of secondary phases (titanium carbides and nitrides) precipitated at dislocation loops and dislocations during annealing at temperatures above 750°C.

Reactor Physics Development for Advanced Gas-Cooled Reactors; Recherches en Physique des Reacteurs, pour des Reacteurs Perfectionnes Refroidis par un Gaz; Razrabotka metodov v oblasti reaktornoj fiziki dlya usovershenstvovannogo reaktora s gazovym okhlazhdeniem; Progresos de la Fisica de los Reactores de Tipo Avanzado Refrigerados por Gas

Energy Technology Data Exchange (ETDEWEB)

Moore, J. [United Kingdom Atomic Energy Authority (United Kingdom)

1964-04-15

metodos de medicion de los efectos de la reactividad en APEX, HERO y AGR, y para determinar los datos relativos a la estructura fina y a la distribucion de la potencia en los conjuntos combustibles complejos. Los trabajos se concentran principalmente en el desarrollo de un metodo capaz de sustituir al 'hetrecontrol' y al 'FTD2' , para los cuerpos de reactor cuando el combustible haya alcanzado un grado de combustion considerable. La finalidad del programa experimental con la instalacion HERO es precisamente comprobar estos metodos con cuerpos complejos, inclusive con combustible que contenga plutonio. La explotacion del reactor AGR y las mediciones fisicas que se realicen con el combustible despues de la irradiacion permitiran obtener datos adicionales sobre el efecto del plutonio. (author) [Russian] Rassmatrivaetsja tshhatel'naja jeksperimental'naja i teoreticheskaja rabota, provedennaja pri konstruirovanii, stroitel'stve i vvode v jekspluataciju Uindskejlskogo usovershenstvovannogo reaktora s gazovym ohlazhdeniem i pri okazanii obshhej pomoshhi pri razrabotke usovershenstvovannogo reaktora s gazovym ohlazhdeniem (AGR) dla proizvodstva jenergii dlja grazhdanskih celej. Daetsja opisanie znachitel'nogo ob{sup e}ma rabot, kotorye byli neobhodimy dlja razrabotki prigodnyh teoreticheskih metodov rascheta: 1) raspredelenija potoka i balansa reaktivnosti v slozhnoj aktivnoj zone reaktora; 2) raspredelenija jenergii v toplive so slozhnoj geometriej i 3) vlijanija obluchenija na toplivnye cikly i raspredelenie jenergii. V kachestve vvedenija delaetsja ssylka na jeksperimental'nye dannye i teoreticheskie metody, poluchennye v rezul'tate rabot nad uranovo-magnoksovymi sistemami, i na jeksperimental'nye dannye, poluchennye v rezul'tate Sovmestnoj jeksperimental'noj programmy Britanskoj promyshlennosti (BICEP), kotorye javilis' otpravnym momentom v razrabotke teoreticheskih metodov, primenimyh k usovershenstvovannym reaktoram s gazovym ohlazhdeniem. Dlja opredelenija parametrov

The First Two Years of Operating Experience of the Kahl Nuclear Power Station; Experience acquise pendant les deux premieres annees de fonctionnement de la centrale nucleaire de Kahl; Opyt pervykh dvukh let ehkspluatatsii atomnoj ehlektrostantsii v Kale; Experiencia adquirida en los primeros cuatro anos de funcionamiento de la central nucleoelectrica de Kahl

Energy Technology Data Exchange (ETDEWEB)

Bruchner, H. J. [Aeg-Kernenergieanlagen, Frankfurt-am-Main (Germany); Weckesser, A. [Versuchs-Atomkraftwerk Kahl Gmbh, Kahl (Germany)

1963-10-15

, une boucle experimentale destinee a l'etude de la surchauffe nucleaire. (author) [Spanish] La central de Kahl constituye la primera central nucleoelectrica europea de propiedad privada, y funciona en carga desde junio de 1961. Esta equipada con un reactor de agua hi que trabaja en ciclo indirecto por circulacion natural. Su capacidad electrica neta asciende a 15 MW y hasta febrero de 1963 habia producido 140 millones de kWh. La memoria revisara la experiencia adquirida durante su funcionamiento, ante todo con el extenso programa de ensayos sobre el comportamiento transitorio y la exploracion gamma. Presentara datos acerca del resultado que han dado en funcionamiento ciertas partes de la central, tales como el dispositivo de accionamiento de las barras de control, el sistema de purificacion de los gases de escape y la turbina. Una vez terminado el programa de ensayos, la planta se exploto en carga basica durante algun tiempo a fin de reunir datos sobre el rendimiento del combustible en la ptactica. Una vez completada esta fase, se instalara en el reactor de Kahl un circuito experimental de sobrecalentamiento nuclear. (author) [Russian] Atomnaya ehlektrostantsiya v Kale, pervaya v Evrope chastnaya atomnaya ehlektrostantsiya, ehkspluatiruetsya pod nagruzkoj s iyunya 1961 goda. Na ehlektrostantsii ustanovlen reaktor s kipyashchej vodoj, kosvennym tsiklom i estestvennoj tsirkulyatsiej. Chistaya ehlektricheskaya moshchnost' reaktora sostavlyaet 15 mgvt. Do fevralya 1963 goda kolichestvo poluchennoj ehnergii sostavilo 140 mln. kvt.ch. Rassmotren opyt ehkspluatatsii, v chastnosti rasshirennaya programma ispytanij: naprimer,povedenie reaktora pri perekhodnom protsesse i kontrol' gamma-izlucheniya. Budut predstavleny rezul'taty izucheniya ehkspluatatsionnoj kharakteristiki nekotorykh komponentov ustanovki, naprimer sistemy privoda reguliruptsikh sterzhnej, sistemy udaleniya gaza i turbiny. Posle osushchestvleniya ehtoj programmy ispytanij ustanovka v techenie nekotorogo vremeni

Annual report of the group for maintenance of electronic equipment; Godisnji izvestaj elektronske grupe

Energy Technology Data Exchange (ETDEWEB)

Popovic, B [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1965-12-15

Maintenance and repair of the RA reactor control and safety systems were uniformly distributed during the whole year and were done according to the annual plan. A series of repairs of he electronic equipment as well as exchange of electronic components and elec tonic tubes. The testing and calibration of control and protection circuits were done regularly according to the needs and operation state of the reactor and according to the instructions. Inspections, repairs and reconstructions well as operating characteristics of individual elements as well as complete electronic circuits during 1965 have shown da the systems of control and safety are still in good condition. Somewhat higher number of failures due to aging of electronic tubes is a regular consequence of equipment and instrumentation aging. [Serbo-Croat] Remontni radovi na opremi sistema za upravljanje i sigurnost reaktora RA ravnomerno su rasporedjeni tokom cele godine i obavljaju se prema planu remonta. Izvrsen je citav niz popravki elektronske instrumentacije, kao i zamena komponenti i elektronskih cevi. Sve kontrole ispravnosti i kalibracije lanaca za upravljanje i zastitu reaktora redovno su vrsene prema potrebi i u vezi sa radnim stanjem reaktora prema uputstvu za ove operacije. Pregledi, remonti i popravke kao i radne karakteristike pojedinih elemenata kao i kompletnih instrumentalnih kontrolnih lanaca u toku 1965. godine pokazali su da su sistemi upravljanja i sigurnosne zastite jos u dobrom stanju. Nesto veci broj kvarova usled starenja elektronskih cevi je normalna posledica starenja opreme i instrumentacije.

New Instruments and Principles for the Dimensional Measurement and Measurement of Spacing of Reactor Components; Nouveaux Instruments et Procedes de Mesure des Dimensions et de l'Espacement des Elements d'un Reacteur; Novye pribory i printsipy izmereniya razmerov i raspolozheniya komponentov reaktora; Nuevos Instrumentos y Principios para Medir las Dimensiones y la Separacion Entre Componentes de Reactor

Energy Technology Data Exchange (ETDEWEB)

Mueller, P. [Institut Dr. Foerster, Reutlingen, Federal Republic of Germany (Germany)

1965-09-15

Full text: The measurement of wall thickness of austenitic and non-ferrous sheets, tubes and containers is presented. Two methods for contactless measurement are discussed: eddy- current method for measuring the thickness of non-ferrous and austenitic sheets and containers by means of transition coils; eddy-current measurement of the wall thickness of tubes by means of feed-through coils. Suitable instruments and their application are shown. Wall-thickness measurement on non-ferrous reactor assemblies by the ''magnetic ball method'' is also discussed. The principle of this new type of measurement is explained, its range of use - especially for spot- measurements - is discussed, and a practical instrument is described. Measurement of non-magnetic coatings on magnetic base materials is discussed. The measurement principles (magnetic DC and AC field methods) are explained and instruments for measurement of nonmagnetic coatings between 3-{mu}m and 20-mm thickness are shown. The special problem of measurement of stellite deposits on ferritic walls of reactor vessels is discussed. The measurement of electrically non-conductive coatings on base materials consisting of non-ferrous metals; and the principle of measurement (eddy currents) are explained. An instrument for this purpose is shown and typical examples of measurements are given. Contactless in-line measurements of physical dimensions of metallic reactor components are given. Various methods for ferrous and non-ferrous metals are explained (magnetic DC and AC field method, eddy-current methods). Instruments and examples for remote measurements of diameter, ovality, distortion etc., of reactor components are described, and methods of measuring the spacing of such components in the ''hot'' zone of the reactor are shown. An instrument for recording the surface profile and for direct reading the roughness values (''Rauhtiefe'', ''Glaettungstiefe'', CLA value and RMS value) is shown. Typical examples of the use of the

Annual report of the mechanics group; Godisnji izvestaj masinske grupe

Energy Technology Data Exchange (ETDEWEB)

Bratic, A [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1965-12-15

Planned maintenance and repair of fundamental reactor systems was done during planned shut down periods in 1965. For that reason there was no interruption of reactor operation caused by failures of the equipment. Planned repairs were concerned with: heavy water system, gas system, technical water system, distillation system, graphite cooling system, ventilation and heating systems and emergency power supply system in the reactor building. This report includes as well, the list of unplanned repairs. [Serbo-Croat] U 1965. godini vrsen je planski remont osnovnih agregata reaktorskih sistema u planiranim periodima stajanja reaktora, te nije doslo ni do kakvih duzih prekida rada reaktora usled kvarova na opremi. Planski remont obuhvatio je: sistem teske vode, gasni sistem, sistem tehnicke vode, sistem destilacije, sistem hladjenja grafita, sistem ventilacije i grejanja, transportne uredjaje, dizel agregata. Ovaj izvestaj sadrzi i listu vanplanskih remonta i popravki.

Special Nuclear Material Control by the Power Reactor Operator; Controle des Matieres Nucleaires Speciales par l'Exploitant d'une Centrale Nucleaire; Spetsial'nyj kontrol' nalichiya yadernykh materialov operatorom ehnergeticheskogo reaktora; Control de Materiales Nucleares Especiales por Parte de Quienes Operan el Reactor de Potencia

Energy Technology Data Exchange (ETDEWEB)

Cordin, R. A. [Yankee Atomic Electric Company, Boston, MA (United States)

1966-02-15

debido a un control deficiente de los combustibles nucleares y a la falta de precision en las operaciones contables. La administracion de materiales nucleares requiere que los explotadores de los reactores de potencia lleven una contabilidad completa y detallada. No es necesario que los documentos sean complejos si lo que se pretende es que sean completos y adecuados. En realidad, la sencillez es sobremanera conveniente. A pesar de que el combustible nuclear es un combustible nuevo y totalmente distinto de los de tipo tradicional, no hay que rodear su utilizacion de ninguna aureola de misterio. El control de los materiales nucleares no es una simple labor de inventario, sino que constituye la base de muchas otras operaciones inherentes a la explotacion de los reactores de potencia, por ejemplo: el transporte del combustible irradiado, su regeneracion con la correspondiente contabilizacion del combustible recuperado y del material producido durante el funcionamiento del reactor, y, por ultimo, el establecimiento de un sistema de seguros adecuado. (author) [Russian] Otnositel'no novoe i chrezvychajno cennoe toplivo dlja proizvodstva jelektrojenergii, a imenno uran, trebuet ochen' tshhatel'nogo ucheta s momenta, kogda operator reaktora prinimaet na sebja material'nuju otvetstvennost' za jetot material, i do togo momenta, kogda jetot material v vide chastichno otrabotannogo topliva peredaetsja na druguju ustanovku, gde regeneriruetsja ostavshajasja chast' ego pervonachal'noj cennosti. Bol'shaja chast' operatorov jenergeticheskih reaktorov, do pojavlenija v svet jadernoj jenergetiki, rabotala na jelektrostancijah s obychnym iskopaemym toplivom i /zhe davno vyrabotala dostatochno polnye i nadezhnye formy kontrolja za ego rashodovaniem. Operator reaktora dolzhen raspolagat' ne menee nadezhnymi sposobami ucheta jadernyh materialov, ispol'zuemyh na ego ustanovke. Jekspluatacija jenergeticheskih reaktorov ne imeet bol'shoj istorii, i na protjazhenii otnositel'no korotkogo perioda

Measurements at the RA Reactor related to the VISA-2 project - Part 3, calculation of VISA-2 samples influence on the reactor reactivity, on the depression of thermal neutron flux in VK-5 channel and VISA-2 samples; Fizicka merenja na reaktoru RA u vezi projekta VISA-2 - III deo, Proracun uticaja uzoraka VISA-2 na reaktivnost reaktora, na depresiju fluksa termalnih neuntrona u kanalu VK-5 i u uzorcima VISA-2

Energy Technology Data Exchange (ETDEWEB)

Markovic, H; Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1962-07-01

The objective of this task was to determine the thermal neutron flux in the RA reactor cell with VISA-2 samples, the influence of VISA-2 samples on the thermal neutron flux distribution in the vicinity of VK-5 channel and the antireactivity of VISA-2 samples placed in the RA reactor core. This distribution is needed for calculating the mean value of absorption and thermal efficiency factor in the reactor cell with the sample. Thermal neutron flux distribution without the sample was calculated by diffusion theory. Fast neutron flux space distribution was assumed to be constant, i.e. that it is dependent only on the nuclear properties of the materials. Macroscopic thermal neutron flux distribution was determined by two-group diffusion theory using the four factor formula applied for two regions: active RA region, and reactor region with calls containing VISA-2 samples. This calculation enables estimation of the VISA-2 samples influence on the thermal neutron flux distribution in the VK-5 channel. Antireactivity of VISA-2 samples was calculated by neutron diffusion theory applying the perturbation method. [Serbo-Croat] Cilj ovog zadatka je da se odredi raspodela fluksa termalnih neutrona u celiji reaktora RA sa uzorcima VISA-2, uticaj uzoraka VISA-2 na makroskopsku raspodelu termalnih neutrona u blizini uzoraka, tj. u kanalu VK-5, kao i antiraktivnost uzoraka VISA-2 ubacenih u jezgro RA. Poznavanje ove raspodele potrebno je za izracunavanje srednje apsorpcije i faktora termalnog iskoriscenja u celiji reaktora sa uzorkom. Raspodela fluksa termalnih neutrona u celiji RA bez uzorka izracunata je na bazi difuzione teorije. Fluks brzih neutrona uzet je kao konstanta s obzirom na prostorne koordinate, tj. da zavisi samo od nuklearnih karakteristika materijala. Makroskopska raspodela fluksa termalnih neutrona u okolini VISA-2 odredjena je na bazi dvogrupne difuzione teorije preko formule cetiri faktora, primenjene na dve zone: prva aktivna zona RA, i druga reaktorka sredina

Report on results of the Experts from the Boris Kidric Institute to the Institute for theoretical and experimental physics in Moscow - Operational Report; Radni izvestaj - Izvestaj o rezultatima posete strucnjaka iz IBK Institutu za teorijsku i eksperimentalnu fiziku u Moskvi

Energy Technology Data Exchange (ETDEWEB)

Martinc, R; Petrovic, M; Cupac, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1976-12-15

.) upoznavanje eksploatacionih karakteristika reaktora TVRS sa 80% obogacenim gorivom, kao i iskustva u vezi sa koriscenjem tog goriva u reaktoru TVRS u Moskvi; b.) upoznavanje sa elementima sigurnosnih analiza u vezi sa uvodjenjem i kriscenjem tog goriva u reaktoru TVRS kao i c.) razmena gledista o programu prevodjenja reaktora RA na novo 80% obogaceno gorivo. U izvestaju su prikazani rezultati ove posete. Osnovni zakljucci do kojih se doslo jesu: a.) poseta je bila korisna i pored toga sto na neka pitanja nije dobijen odgovor; b.) posle obrade dobijenih informacija, posle sticanja prvih iskustava o koriscenju novog goriva u reaktoru RA kao i posle donosenja definitivnog suda o ravnoteznom rezimu reaktora RA sa novim gorivom, bilo bi veoma korisno da se izvrsi jos jedna poseta Institutu u Moskvi; c.) novo disperziono gorivo je mnogo pouzdanije u eksploataciji od starog 2% obogacenog metalnog goriva (kakvo je sada u reaktoru RA); d.) nije bilo primedbi sa aspekta sigurnosti na nas program prevodjenja (prelazni rezim) reaktora RA na novo gorivo; e.) zatrazice se dopunske informacije o maksimalnom dopustivom stepenu izgaranja 80% obogacenog disperzionog goriva i po potrebi izvrsice se blagovremena revizija predvidjenog optimalnog ravnoteznog rezima izgaranja za reaktor RA (baziranog na maksimalnom izgaranju goriva koje omogucuju parametri reaktora RA); f.) metodologija termickog proracuna gorivnih kanala, koja se primenjuje na reaktor RA ocenjena je kao ekvivalentna postupku koji se primenjuje za proracun kanala reaktora TVRS u Moskvi (author)

LED Current Balance Using a Variable Voltage Regulator with Low Dropout vDS Control

Directory of Open Access Journals (Sweden)

Hung-I Hsieh

2017-02-01

Full Text Available A cost-effective light-emitting diode (LED current balance strategy using a variable voltage regulator (VVR with low dropout vDS control is proposed. This can regulate the multiple metal-oxide-semiconductor field-effect transistors (MOSFETs of the linear current regulators (LCR, maintaining low dropout vDS on the flat vGS-characteristic curves and making all drain currents almost the same. Simple group LCRs respectively loaded with a string LED are employed to implement the theme. The voltage VVdc from a VVR is synthesized by a string LED voltage NvD, source voltage vR, and a specified low dropout vDS = VQ. The VVdc updates instantly, through the control loop of the master LCR, which means that all slave MOSFETs have almost the same biases on their flat vGS-characteristic curves. This leads to all of the string LED currents being equal to each other, producing an almost even luminance. An experimental setup with microchip control is built to verify the estimations. Experimental results show that the luminance of all of the string LEDs are almost equal to one another, with a maximum deviation below 1% during a wide dimming range, while keeping all vDS of the MOSFETs at a low dropout voltage, as expected.

Reactor utilization; Eksploatacija reaktora

Energy Technology Data Exchange (ETDEWEB)

Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

1963-02-15

In 1962, the RA reactor was operated almost three times more than in 1961, producing total of 25 555 MWh. Diagram containing comparative data about reactor operation for 1960, 1961, and 1962, percent of fuel used and U-235 burnup shows increase in reactor operation. Number of samples irradiated was 659, number of experiments done was 16. mean powered level was 5.93 MW. Fuel was added into the core twice during the reporting year. In fact the core was increased from 56 to 68 fuel channels and later to 84 fuel channels. Fuel was added to the core when the reactivity worth decreased to the minimum operation level due to burnup. In addition to this 5 central fuel channels were exchanged with fresh fuel in february for the purpose of irradiation in the VISA-2 channel.

Theoretical analysis of nuclear reactors (Phase II), I-V, Part V, Determining the fine neutron flux distribution by Pn method; Razrada metoda teorijske analize nuklearnih reaktora (II faza) I-V, V Deo, Odredjivanje fine raspodele fluksa Pn metodom

Energy Technology Data Exchange (ETDEWEB)

Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1962-10-15

Expression for spherical harmonic moments were applied. They were obtained by spherical harmonics expansion of monoenergetic transport equation. This report presents the procedure for calculating the neutron flux distribution in the nine-zone reactor cell of the RA reactor in Vinca. The procedure was modelled for digital computer ZUSE Z-23 by expansion of the diagram of the automated P{sub 3} code, which is adequate for P{sub n} code with minor changes. The needed subroutines were developed. The most important ones were those for modified first and second order Bessel functions of n-th order. Computer Z-23 was operating only 15 hours during three months, and thus only the subroutines for modified Bessel functions could be tested and the obtained results were excellent. For the mentioned reason the neutron flux distribution will be calculated in the forthcoming period. Koriscen je izraz za svernoharmonicne momente koji se dobija razvijanjem monoenergetske transportne jednacine u sverne harmonike. Dat je postupak za odredjivanje raspodele neutronskog fluksa u devet medijalnoj celiji reaktora RA u Vinci. Gornji postupak je logicki organizovan na digitalnoj masini ZUSE Z-23 razvijanjem tekuceg dijagrama automatskog P{sub 3} koda, koji sa malim izmenama odgovara Pn kodu. Razvijene su potrebne osnovne subrutine, medju kojima su najznacajnije one za modificirane Beselove funkcije prve i druge vrste n - tog reda. Masina ZUSE Z-23 bila je u radu svega 15 zasova u toku tri meseca, te sam stigao da testiram samo subrutine za modificirane Beselove funkcije koje su dale odlicne rezultate. Iz ovoga razloga nije se mogla dobiti trazena raspodela fluksa. To ce biti ucinjeno u narednom periodu posto cemo moci koristiti masinu Z-23 (author)

RA Research nuclear reactor, Part 1, RA reactor operation and maintenance in 1993, with comparative review for the period 1991 - 1993, Annex 3; Projekat Istrazivacki nuklearni reaktor RA - 1 Deo Pogon i odrzavanje nuklearnog reaktora RA u 1993. godini, uz uporedni pregled za period 1991 - 1993. - prilog 3

Energy Technology Data Exchange (ETDEWEB)

Sotic, O; Cupac, S; Sulem, B; Zivotic, Z; Mikic, N; Tanaskovic, M [Vinca Institute of Nuclear Sciences, Beograd (Serbia and Montenegro)

1993-12-15

RA reactor was not operated during 1993 because of the complete instrumentation exchange. Although it has been planned to exchange the complete instrumentation until the end of 1993, and to start reactor operation in the first half of 1993 this was not fulfilled because the instrumentation was not delivered until the end of 1993. Main activities during past seven years were related to construction of the emergency cooling system; repair and reconstruction of the system for handling the spent fuel and improvement of spent fuel storage conditions; exchange of the aged instrumentation. Other reactor components and systems, reactor core, primary coolant loop and gas circulation system are in good condition concerning future start-up. [Serbo-Croat] U 1993. godini reaktor nije bio u pogonu zbog zamene njegove celokupne instrumentacije. Iako je bilo planirano da se celokupna instrumentacija zameni do kraja 1993. te da reaktor pocne sa radom u prvoj polovini 1993. Ovo nije ispunjeno jer celokupna oprema nije isporucena ni do kraja 1993. godine. Osnovni zahvati koji su u proteklih sedma godina izvrseni, odnosili su se na izgradnju sistema za udesno hladjenje, rekonstrukciju sistema za rukovanje ozracenim gorivom i poboljsanje uslova za stokiranje ovog goriva, zamenu instrumentacije. Ostali sistemi reaktora, reaktorsko jezgro, primarno kolo hladjenja i sistem za cirkulaciju gasa su u dobrom stanju i mogu se nesmetano koristiti u buducem radu.

A pulsed fast reactor; Un reacteur pulse a neutrons rapides; Impul'snyj reaktor na bystrykh nejtronakh; Reactor rapido pulsado

Energy Technology Data Exchange (ETDEWEB)

Blokhin, G. E.; Blokhintsev, D. I.; Blyumkina, Yu. A.; Bondarenko, I. I.; Deryagin, B. N.; Zajmovskij, A. S.; Zinov' ev, V. P.; Kazachkovskij, O. D.; Krasnoyarov, N. V.; Lejpunskij, A. I.; Malykh, V. A.; Nazarov, P. M.; Nikolaev, S. K.; Stavisskij, Yu. Ya.; Ukraintsev, F. I.; Frank, I. M.; Shapiro, F. Ji.; Yazvitskij, Yu. S. [Akademiya Nauk, Moscow, SSSR (Russian Federation)

1962-03-15

los impulsos de potencia. Asimismo, se efectuaron mediciones del periodo de los neutrones instantaneos, de la fraccion efectiva de neutrones retardados y de los coeficientes de variacion de la reactividad en funcion de la temperatura. (author) [Russian] Impul'snyj reaktor na bystrykh nejtronakh (IBR) rabotaet na nominal'noj moshchnosti v Obedinennom institute yadernykh issledovanij s dekabrya 1960 goda. Reaktor ispol'zuetsya v kachestve impul'snogo istochnika nejtronov dlya fizicheskikh ehksperimentov, provodimykh metodom vremeni proleta. Provodyatsya izmereniya polnogo secheniya, secheniya zakhvata dlya promezhutochnykh nejtronov, issledo- vaniya vzaimodejstviya medlennykh nejtronov s tverdym telom i s zhidkost'yu, izmereniya spektrov nejtronov, ustanavlivayushchikhs ya v. razlichnykh sredakh. V doklade opisany osnovy konstruktsii reaktora i rezul'taty ego issledovanij. Osnovnoj rezhim raboty reaktora-rezhim periodicheskikh impul'sov. Impul'sy moshchnosti voznikayut pri bystrom peremeshchenii podvizhnoj chasti aktivnoj zony reaktora cherez ego nepodvizhnuyu zonu. Podvizhnaya chast' aktivnoj zony zakreplena vo vrashchayushchemsya diske i dvizhetsya so skorost'yu-230 m/sek. Chastota impul'sov moshchnosti mozhet izmenyat'sya s pomoshch'yu vspomogatel'noj podvizhnoj zony v diapazone 2,3-88 im/sek. Srednyaya moshchnost' reaktora - 1 kvt. Polushirina impul'sa moshchnosti - 36 mksek. Reaktor snabzhen sistemoj upravleniya i zashchity, obespechivayushchej avtomaticheskoe podderzhanie srednej moshchnosti reaktora i ego bystruyu ostanovku v sluchae narusheniya rezhima. Reaktor snabzhen sistemoj vakuumirovanny kh nektronovodov, ispol'zuemykh v ehksperimentakh po vremeni proleta. Glavnyj nejtronovod imeet dlinu 1000 m. V protsesse puska i fizicheskikh issledovanij reaktora izuchalos' vliyanie peremeshcheniya organov regulirovaniya i podvizhnykh chastej aktivnoj zony na reaktivnost', izmeryalas' dlitel'nost' impul'sa pri razlichnykh rezhimakh raboty reaktora, izuchalis

Operational report, Advantages of gradual introducing of highly enriched fuel into the RA reactor core from economic aspect and users needs; Radni izvestaj, Prednost postupka parcijalnog uvodjenja visokoobogacenog goriva u reaktor RA sa aspekta ekonomicnosti i potreba korisnika

Energy Technology Data Exchange (ETDEWEB)

Martinc, R et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1976-10-14

The possibility of increasing the neutron flux in the RA reactor was considered for a number of years. The possibilities of reactor reconstruction are not realistic and they should be disregarded. The possibility that remains is to achieve higher neutron flux by improving the fueling scheme and above all by introducing highly enriched fuel into the reactor core. Decision to purchase highly enriched fuel was quicker due to the fact that the 2% enriched uranium fuel is not fabricated any more. There are two procedures for exchanging the fuel in the reactor core: a) removal of partially spent 2% enriched fuel and formation of the core with fresh highly enriched fuel; b) gradually introducing the new fuel into the existing RA reactor core according to a special transfer regime. This report includes some comparative analyses of these two procedures from both economic point of view and the needs of users, as well as some technical conditions. These results are in favour of gradual introducing of new fuel into the reactor core. relevant direct savings amount to 3 000 000 dinars. Some of the most important advantages cannot be estimated in this way. This report does not cover the safety analyses results which are presented in a series of other papers. [Serbo-Croat] Vec vise godina razmatra se mogucnost za povecanje neutronskog fluksa u reaktoru RA. Mogucnosti za rekonstrukciju reaktora RA u tom smislu su minimalne i realno ih treba odbaciti. Prema tome preostaje da se povecanje neutronskog fluksa postigne usavrsavanjem seme izmene goriva, a pre svega uvodjenjem goriva sa visokim stepenom obogacenja u reaktor RA. Donosenje odluke o nabavci visokoobogacenog goriva i njegovom uvodjenju u reaktor ubrzano je i cinjenicom da se staro 2% obogaceno uransko gorivo vise ne proizvodi. Postoje dva postupka za prevodjenje reaktora na ovo gorivo: a) Uklanjanjem poluistrosenog 2% obogacenog goriva iz reaktora i formiranjem jezgra iskljucivo od svezeg visokoobogacenog goriva, b

Assessing cadmium distribution applying neutron radiography in moss trophical levels, located in Szarvasko, Hungary

Energy Technology Data Exchange (ETDEWEB)

Varga, J.; Koroesi, F. E-mail: fkorosi@hotmail.com; Balasko, M. E-mail: balasko@sunserv.kfki.hu; Naar, Z

2004-10-01

The measuring station of the 10 MW VVR-SM research reactor at the Budapest Neutron Centre (Hungary) was used to perform dynamic neutron radiography (DNR), which was, to our best knowledge, the first time, in a Tortella tortuosa biotope. In the conducted study, two trophical levels, moss and spider Thomisidae sp. juv., were examined. Cadmium penetration routes, distribution and accumulation zones were visualized in the leafy gametophyte life cycle of Tortella tortuosa and in the organs of the spider.

Progress report

International Nuclear Information System (INIS)

Brumovsky, M.

1979-01-01

Progress Report, covering the period up to the end of 1979 year, was sent to the IAEA according to the research agreement No. 1971 /CF. This work covered the following fields: preparation and dummy irradiation experiments with a new experimental capsule of ''CHOUCA-M'' type; measurement of temperature fields and design of specimen holders; measurement of neutron energy spectrum in the irradiation place in our experimental reactor of VVR-S type (Nuclear Research Institute) using a set of activation detectors; unification and calibration of the measurement of neutron fluence with the use of Fe, Cu, Mn-Mg and Co-Al monitors; development and improvement of the measuring apparatus and technique for the dynamic testing of pre-cracked specimens with determination of dynamic parameters of fracture mechanics; preparation and manufacture of testing specimens from the Japanese steels - forging, plate and weld metal; preparation of the irradiation capsule for assembling

Securing of the spent nuclear fuel stored on Gremikha site - the former Soviet submarine base in north-west of Russia - 59371

International Nuclear Information System (INIS)

Gorbatchev, Alexandre; Pillette-Cousin, Lucien; Stepennov, Boris; Eremenko, Valery; Zakharchev, Anatoly

2012-01-01

Document available in abstract form only. Full text of publication follows: In the framework of the G8 Global Partnership the French Commission on Atomic Energy (CEA) is in charge of the French funded projects aimed to secure the materials susceptible to be a subject of the proliferation or a malicious use. The securing of the Spent Nuclear Fuel (SNF) from the former soviet submarines is of a special importance for CEA and the Russian Rosatom. Our main bilateral project has focused on two kinds of the SNF (alpha cores and VVR assemblies) stored at Gremikha, the former submarine base in the North-West of Russia. As of 2011 a significant results have been achieved: 2/3 of VVR type assemblies have been removed from Gremikha and reprocessed at PO Mayak. Nine alpha cores are unloaded and stored on at Gremikha. The main task now is to prepare the removal from Gremikha of all the remaining SNF and also to set up the needed infrastructure at the sites where this SNF will be moved. Substantial funding and technical assistance both from France and Russia will be required for that. Beyond the operator of the Gremikha site (SevRAO), the CEA and Rosatom involve many expert organizations from both countries such as AREVA, Kurchatov Institute and many others. Their contribution is one of the key elements of the success. (authors)

RA Research reactor, Annual report 1972; Istrazivacki nuklearni reaktor RA - Izvestaj za 1972. godinu - Pogon i odrzavanje

Energy Technology Data Exchange (ETDEWEB)

Milosevic, D et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1972-12-15

During 1972, the total production was 31151 MWh which is 3.8% higher than planned. The reactor was used for irradiation and experiments according to the demand of 381 users, of which 340 from the Institute and 41 external users. This report contains detailed data about reactor power and experiments performed in 1972. Discrepancies from the action plan, meaning higher production was achieved due to special demands of the users. Total number of interruptions was lower than during all the previous years, and were caused mainly due to announced power cuts. There was only on scram shutdown during this year caused by a false signal of the reactor control instrumentation. There were no longer interruptions. One shorter interruption (shorter than 24 hours) caused by removal of a UO{sub 2} capsule from the core, placed there for measuring heat transfer. Total personnel exposure dose was lower than during previous years. One accident caused contamination with gases and aerosols containing mainly shot-living isotopes. Decontamination od surfaces was less than during previous years. Practically there was no surface contamination that would demand action of the decontamination team, except for the regular decontamination after refueling. It was concluded that the successful operation in 1972 has a special significance having taking in account the financial crisis caused by the unresolved status of the reactor. It is emphasised, in the plan for the next year that there is an urgent need of making a long-term plan of rector application. It is indispensable to finish preparatory tasks for replacing the fuel with the highly enriched fuel elements by 1974, and building the core emergency cooling system. [Serbo-Croat] Ukupni rad Reaktora RA je u 1972. godini iznosio je 31151 MWh odnosno 3,8% vise od planiranog. Reaktor je koriscen za ozracivanja i eksperimente za 381 korisnika od cega 340 iz Instituta i 41 za korisnike izvan Instituta. Ovaj izvestaj sadrzi detaljne podatke o radu i

Veeravalli Venkata Ranga Varadachari (01 July 1925- 04 August 2007)

Digital Repository Service at National Institute of Oceanography (India)

Murty, C.S.

/advise a good number of people suffering from chronic problems. One patient (who lives abroad, name withheld here for anonymity) was so pleased with the results after following the course of treatment suggested to her that she offered a laptop computer... during those times in Andhra Pradesh. After a year's service with the Government's Department of Defence Accounts at Jabalpur, to meet the finances required for higher studies, VVR got himself enrolled as a student at the Andhra University's College...

Report on the activity of the RA reactor operation for the period from July 1 1961 - Sept. 30 1961; Tromesecni izvestaj za period od 1.VII do 30.IX 1961. g

Energy Technology Data Exchange (ETDEWEB)

Zecevic, V [Laboratorija za eksploataciju reaktora RA, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1961-09-15

During the reporting period the reactor was permanently ready for operation and responding to the demands of the experimenters. The reactor was operating for 408.5 hours at power levels from 50 - 5000 kW, or 1985 MWh in total, burnup of the first batch of fuel was 22.55%. Reactor core was made of 56 fuel channels. Activities related to construction of new and improvement of the existing equipment was continued in order to enable safe operation and successful utilization of the RA reactor. Exchange of the electronic tubes was continued in order to increase the stability of the reactor control and reactor protection systems. About 65% of tubes planned to be exchanged this year was done. Cooperation with the CEN Saclay, France related to construction of experimental loops VISA-1 and VISA-2 was continued as well as cooperation with Poland concerned with exchange of experts. The problem of lack of properly trained staff was nor solved. [Serbo-Croat] U izvestajnom periodu reaktor je uvek bio spreman za rad i odgovarao je zahtevima eksperimentatora. Reaktor je radio 408,5 casova na snagama od 50-5000 kW, odnosno ukupno 1985 MWh, pri cemu je ukupan utrosak prve sarze goriva bio 22,55%. Jezgro reaktora bilo je sacinjeno od 56 tehnoloskih kanala. Radi bezbednijeg pogona i sto uspesnije eksploatacije reaktora RA nastavljeno je sa radovima na realizaciji novih i poboljsanju postojecih uredjaja. U cilju povecanja stabilnosti elektronskih instrumenta u sistemu upravljanja i zastiti reaktora nastavljeno je sa zamenom elektronskih cevi, do sada je zamenjeno oko 65% radova predvidjenih za ovu godinu. Nastavljena je saradnja sa nuklearnim centrom u Saclay, Francuska na izradi petlje VISA-1 i VISA-2 i saradnja sa Poljskom u razmeni strucnjaka. Problem nedostatka kadrova nije resen.

Report of the Technology Service - Annex B; Prilog B - Izvestaj o radu tehnoloske sluzbe

Energy Technology Data Exchange (ETDEWEB)

Cupac, S; Vukadin, Z [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1992-01-01

This annex covers: description of the organisational structure of the service, safeguard activities, increase of reactor operation capability, dosimetry and radiation protection tasks and an overview of the the activities of this Service. During 1992, there have been 12 safeguard IAEA inspections. Each time inspection covered fresh fuel, every third inspection included control of the spent fuel storage pool, and once during the fuel inventory control the reactor core was included. With the aim of increasing the operating capabilities besides improvement of experimental devices, construction of the experimental loop with separate cooling system was started. It is planned, as well to improve operating capabilities of horizontal experimental channels by purchasing neutron diffractometer, constructing three-crystal neutron spectrometer, application of three-crystal neutron spectrometer from Krakow, and using the time-of flight spectrometer constructed in the Institute. This Annex describes the possible activities for neutron radiography and isotope production, and includes radiation protection data. [Serbo-Croat] Ova prilog sadrzi opis organizacije tehnoloske sluzbe, 'safeguard' aktivnosti, moguce poboljsanje eksploatacionih mogucnosti reaktora, tehnicke zastite od zracenja i dozimetrije, kao i pregled svih poslova Sluzbe. Tokom 1992. bilo je 12 'safeguard' IAEA inspekcija. Tokom svake inspekcije kontrolisano je sveze gorivo, svaka treca je ukljucila kontrolu bazena za odlezavanje ozracenog goriva, a jednom je kontrolisano i jezgro reaktora RA. Sa ciljem da se poboljsaju operativne mogucnosti reaktora, pored poboljsanja eksperimentalnih uredjaja, pocela je i izgradnja reaktorske petlje sa sopstvenim hladjenjem. Planirano je da se poboljsaju i operativne mogucnosti horizontalnih eksperimentalnih kanala, sto je ucinjeno kupovinom neutronskog difraktometra, izgradnjom trikristalnog neutronskog spektrometra, koriscenjem trikristalnog neutronskog spektrometra koji je

Accident conditions analysis of spent fuel storage pool RA research reactor in Vinca; Analiza udesnih stanja u odlagalistu isluzenog goriva istrazivackog rektora RA u Vinci

Energy Technology Data Exchange (ETDEWEB)

Jovic, V; Jovic, L [Institute of Nuclear Sciences VINCA, Belgrade (Serbia and Montenegro)

2000-07-01

Based on Safety analysis of the spent fuel pool RA research reactor in Vinca, conditions and possibilities accident sequences in present configuration storage facility are considered (author) [Serbo-Croat] Na osnovu Analize sigurnosti odlagalista isluzenog goriva istrazivackog reaktora RA u Vinci razmatraju se uslovi i mogucnosti pojave udesnih stanja u postojecoj konfiguraciji odlagalista (author)

A binary mixed integer coded genetic algorithm for multi-objective optimization of nuclear research reactor fuel reloading

Energy Technology Data Exchange (ETDEWEB)

Binh, Do Quang [University of Technical Education Ho Chi Minh City (Viet Nam); Huy, Ngo Quang [University of Industry Ho Chi Minh City (Viet Nam); Hai, Nguyen Hoang [Centre for Research and Development of Radiation Technology, Ho Chi Minh City (Viet Nam)

2014-12-15

This paper presents a new approach based on a binary mixed integer coded genetic algorithm in conjunction with the weighted sum method for multi-objective optimization of fuel loading patterns for nuclear research reactors. The proposed genetic algorithm works with two types of chromosomes: binary and integer chromosomes, and consists of two types of genetic operators: one working on binary chromosomes and the other working on integer chromosomes. The algorithm automatically searches for the most suitable weighting factors of the weighting function and the optimal fuel loading patterns in the search process. Illustrative calculations are implemented for a research reactor type TRIGA MARK II loaded with the Russian VVR-M2 fuels. Results show that the proposed genetic algorithm can successfully search for both the best weighting factors and a set of approximate optimal loading patterns that maximize the effective multiplication factor and minimize the power peaking factor while satisfying operational and safety constraints for the research reactor.

A binary mixed integer coded genetic algorithm for multi-objective optimization of nuclear research reactor fuel reloading

International Nuclear Information System (INIS)

Binh, Do Quang; Huy, Ngo Quang; Hai, Nguyen Hoang

2014-01-01

This paper presents a new approach based on a binary mixed integer coded genetic algorithm in conjunction with the weighted sum method for multi-objective optimization of fuel loading patterns for nuclear research reactors. The proposed genetic algorithm works with two types of chromosomes: binary and integer chromosomes, and consists of two types of genetic operators: one working on binary chromosomes and the other working on integer chromosomes. The algorithm automatically searches for the most suitable weighting factors of the weighting function and the optimal fuel loading patterns in the search process. Illustrative calculations are implemented for a research reactor type TRIGA MARK II loaded with the Russian VVR-M2 fuels. Results show that the proposed genetic algorithm can successfully search for both the best weighting factors and a set of approximate optimal loading patterns that maximize the effective multiplication factor and minimize the power peaking factor while satisfying operational and safety constraints for the research reactor.

Research nuclear reactor RA - Annual Report 1991; Istrazivacki nuklearni reaktor RA - Izvestaj za 1991. godinu

Energy Technology Data Exchange (ETDEWEB)

Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1992-01-01

Activities related to revitalisation of the RA reactor stared in 1986, were continued in 1991. A number of interventions on the reactor components were finished that are supposed to enable continuous and reliable operation. The last, and at the same time largest action, related to exchange of complete reactor instrumentation is underway, but it is behind the schedule in 1991 because the delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 56% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. In 1991 most of the existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Construction of some support elements is almost finished by the local staff. The Institute has undertaken this activity in order to speed up the ending of the project. If all the planned instrumentation would not arrive until the end of March 1992, it would not be possible to start the RA reactor testing operation in the first part of 1993, as previously planned. In 1991, 53 staff members took part in the activities during 1991, which is considered sufficient for maintenance and repair conditions. Research reactor RA Annual report for year 1991 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U 1991. godini nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci

RA Research reactor, Annual report 1986; Istrazivacki nuklearni reaktor RA - Izvestaj za 1986. godinu

Energy Technology Data Exchange (ETDEWEB)

Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1986-12-01

Research reactor RA Annual report for year 1985 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1986 godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA.

RA research nuclear reactor - Annual report 1985; Istrazivacki nuklearni reaktor RA - Izvestaj za 1985. godinu

Energy Technology Data Exchange (ETDEWEB)

NONE

1985-12-01

Research reactor RA Annual report for year 1985 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1985 godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA.

Variation of the dimensions and the strength of electrical ceramics during irradiation

International Nuclear Information System (INIS)

Blaunshtein, I.M.; Kishinevskaya, M.B.; Muminov, M.I.

1988-01-01

Changes were studied in the linear dimensions and the ultimate bend strength of a wide range or ceramic materials (MK and GB7 high-alumina ceramics, the UF-46 mullite-corundum ceramic, SNTs and SK-1 steatite ceramics, and the glasses that have the same chemical composition as that of the glass phase of the GB-7 and UF-46 ceramics) following irradiation with a gamma beam from a Co 60 source and in the field of mixed gamma-neutron radiation from a VVR-SM reactor up to the maximum doses

Methods for measuring nuclear properties of materials, Safety coefficient method and measurement of effective absorption coefficient of graphite by safety coefficient method; Razvijanje metoda merenja nuklearnih karakteristika materijala, Razrada metode koeficijenta opasnosti i merenje efektivnog apsorpcionog preseka grafita metodom koeficijenta opasnosti

Energy Technology Data Exchange (ETDEWEB)

Maglic, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1962-11-15

Reactivity of a reactor depends on production, absorption and leaking of neutrons. Change of absorption causes reactivity change, and this fact is used for determining the neutron absorption cross section for the sample inserted in the reactor core. Method for determining the absorption cross section based on reactivity change is called method of safety coefficient. Measurements of neutron absorption cross section for graphite was done in the RA reactor vertical experimental channel VK-5. taking into account the results obtained for five types of graphite this method is considered to be reliable for use. Comparison of nuclear properties of different types of graphite was done as well. Reaktivnost reaktora zavisi od proizvodnje neutrona, apsorpcije i isticanja neutrona. Promena apsorpcije izaziva promene reaktivnosti reaktora pa se ova osobina koristi za odedjivanje neutronskog apsorpcionog preseka uzorka koji se unosi u reaktor. Metoda merenja apsorpcionog preseka na bazi promene reaktivnosti nazvana je metodom koeficijenta opasnosti. Merenje apsorpcionog preseka grafita uradjeno je na reaktoru RA u vertikalnom eksperimentalnom kanalu VK-5. S obzirom na rezultate koji su dobijeni za pet vrsta grafita moze se smatrati da je opravdano koriscenje ove metode. Izvrseno je i poredjenje nuklearnih osobina pomenutih tipova grafita.

Research nuclear reactor RA - Annual Report 1996; Istrazivacki nuklearni reaktor RA - Izvestaj za 1996. godinu

Energy Technology Data Exchange (ETDEWEB)

Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1996-12-01

Activities related to revitalisation of the RA reactor started in 1986, were continued in 1996. All the planned actions related to renewal of the reactor components were finished. The last, and at the same time most important action, related to exchange of complete reactor instrumentation is underway, delayed. The delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 80% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 43 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved. Research reactor RA Annual report for year 1996 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U toku 1996. godine nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Izradu ove opreme finansira Medjunarodna agencija za atomsku energiju kroz ugovor sklopljen decembra 1988. godine sa moskovskom firmom Atomenergoexport. Prema tom

Research nuclear reactor RA - Annual Report 1995, with comparative review for period 1991-1995; Istrazivacki nuklearni reaktor RA - Izvestaj za 1995. godinu, uz uporedni pregled za period 1991-1995

Energy Technology Data Exchange (ETDEWEB)

Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1995-12-01

Activities related to revitalisation of the RA reactor started in 1986, were continued during period 1991-1995. All the planned actions related to renewal of the reactor components were finished. The last, and at the same time most important action, related to exchange of complete reactor instrumentation is underway, delayed. The delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 56% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 47 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved during the period 1991-1995. This research reactor RA Annual is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U periodu 1991-1995. godina nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Izradu ove opreme finansira Medjunarodna agencija za atomsku energiju kroz ugovor sklopljen decembra 1988. godine sa moskovskom

Adverse Reactions in Allogeneic Blood Donors: A Tertiary Care Experience from a Developing Country.

Science.gov (United States)

Sultan, Sadia; Baig, Mohammad Amjad; Irfan, Syed Mohammed; Ahmed, Syed Ijlal; Hasan, Syeda Faiza

2016-03-01

Fragmented blood transfusion services along with an unmotivated blood donation culture often leads to blood shortage. Donor retention is crucial to meet the increasing blood demand, and adverse donor reactions have a negative impact on donor return. The aim of this study was to estimate adverse donor reactions and identify any demographic association.  . We conducted a prospective study between January 2011 and December 2013. A total of 41,759 healthy donors were enrolled. Professionally trained donor attendants drew blood and all donors were observed during and following donation for possible adverse events for 20 minutes. Blood donors were asked to report if they suffered from any delayed adverse consequences.  . Out of 41,759 blood donors, 537 (1.3%) experienced adverse reactions. The incidence was one in every 78 donations. The mean age of donors who experienced adverse events was 26.0±6.8 years, and all were male. Out of 537 donors, 429 (80%) developed vasovagal reaction (VVR), 133 (25%) had nausea, 63 (12%) fainted, 35 (6%) developed hyperventilation, 9 (2%) had delayed syncope, and 9 (2%) developed hematoma. Arterial prick, nerve injury, cardiac arrest, and seizures were not observed. Donors aged less than donors also had a significant association with fainting and nausea, respectively (p adverse events was low at our tertiary center. A VVR was the predominant adverse reaction and was associated with age and weight. Our study highlights the importance of these parameters in the donation process. A well-trained and experienced phlebotomist and pre-evaluation counseling of blood donors could further minimize the adverse reactions.

Neutronics analysis of Dalat Research Reactor

International Nuclear Information System (INIS)

Pham Van Lam; Luong Ba Vien; Le Vinh Vinh; Huynh Ton Nghiem; Nguyen Kien Cuong; Nguyen Manh Hung; Pham Hong Son; Tran Quoc Duong

2006-01-01

Many neutronics codes have been used to calculate for Dalat Research Reactor (DRR) from 1983 (the first critical of DRR in December, 1983). The purposes of all calculations are to know exactly many important parameters related to Reactor Physics and Neutron Physics in reactor core. The results from calculation play important role in core and fuel management for DRR. Especially basing on the results we can predict about fuel cycle, fuel burn up distribution and plan for using optimize remain fresh fuel assemblies of DRR. By using system neutronics code including transport codes, diffusion codes and Mote Carlo code, many characteristics of fuel assemblies and other parameters of whole core were received such as main features of VVR-M2 fuel assembly type, multiplication factor, neutron flux distribution, power distribution, burn up distribution, excess reactivity, control rods worth, neutron spectrum, temperature reactivity coefficient ect. In the paper, brief description all computer codes to being used in DRR and the calculation results from the codes above are presented. (author)

Methods and instrumentation for investigating Hall sensors during their irradiation in nuclear research reactors

International Nuclear Information System (INIS)

Bolshakova, I.; Holyaka, R.; Makido, E.; Marusenkov, A.; Shurygin, F.; Yerashok, V.; Moreau, P. J.; Vayakis, G.; Duran, I.; Stockel, J.; Chekanov, V.; Konopleva, R.; Nazarkin, I.; Kulikov, S.; Leroy, C.

2009-01-01

Present work discusses the issues of creating the instrumentation for testing the semiconductor magnetic field sensors during their irradiation with neutrons in nuclear reactors up to fluences similar to neutron fluences in steady-state sensor locations in ITER. The novelty of the work consists in Hall sensor parameters being investigated: first, directly during the irradiation (in real time), and, second, at high irradiation levels (fast neutron fluence > 10 18 n/cm 2 ). Developed instrumentation has been successfully tested and applied in the research experiments on radiation stability of magnetic sensors in IBR-2 (JINR, Dubna) and VVR-M (PNPI, Saint-Petersburg) reactors. The 'Remote-Rad' bench consists of 2 heads (head 1 and head 2) bearing investigated sensors put in a ceramic setting, of electronic unit, of personal computer and of signal lines. Each head contains 6 Hall sensors and a coil for generating test magnetic field. Moreover head 1 contains thermocouples for temperature measurement while the temperature of head 2 is measured by thermo-resistive method. The heads are placed in the reactor channel

The development of depletion program coupled with Monte Carlo computer code

International Nuclear Information System (INIS)

Nguyen Kien Cuong; Huynh Ton Nghiem; Vuong Huu Tan

2015-01-01

The paper presents the development of depletion code for light water reactor coupled with MCNP5 code called the MCDL code (Monte Carlo Depletion for Light Water Reactor). The first order differential depletion system equations of 21 actinide isotopes and 50 fission product isotopes are solved by the Radau IIA Implicit Runge Kutta (IRK) method after receiving neutron flux, reaction rates in one group energy and multiplication factors for fuel pin, fuel assembly or whole reactor core from the calculation results of the MCNP5 code. The calculation for beryllium poisoning and cooling time is also integrated in the code. To verify and validate the MCDL code, high enriched uranium (HEU) and low enriched uranium (LEU) fuel assemblies VVR-M2 types and 89 fresh HEU fuel assemblies, 92 LEU fresh fuel assemblies cores of the Dalat Nuclear Research Reactor (DNRR) have been investigated and compared with the results calculated by the SRAC code and the MCNP R EBUS linkage system code. The results show good agreement between calculated data of the MCDL code and reference codes. (author)

Program of critical experiment and measurements at the RA reactor; Program kriticnih eksperimenata i merenja na reaktoru RA

Energy Technology Data Exchange (ETDEWEB)

NONE

1960-04-14

Program described in this document describes in detail the following experiments: critical experiments with two reactor core lattices with 38 and 44 fuel channels, initial heavy water level being 1300 mm, criticality is achieved by adding heavy water; preliminary analysis of heavy water quality and verification of the fuel isotopic contents; experiment with the initial core which contains 56 fuel channels with maximum heavy water level according to the Russian proposal; measurement of neutron flux by Dy and In foils; measurement of reactivity excess dependent on the heavy water level and number of fuel rods; measurement of reactor period for determined reactivity change; measurement of moderator temperature coefficient; measurement of absolute flux. [Serbo-Croat] Program sadrzan u ovom dokumentu opisuje detaljno sledece eksperimente: kriticni eksperiment sa dve konfiguracije jezgra reaktora, sa 38 i 44 gorivna kanala, pocetni nivo teske vode je 1300 mm, kriticnost se dostize dodavanjem teske vode; prethodno izvrsenom analizom teske vode i proverom izotopskog sastava goriva; eksperiment sa pocetnom resetkom koja prema ruskom predlogu sadrzi 56 gorivnih kanala i maksimalnom visinom teske vode; merenje raspodele neutronskog fluksa folijama Dy i In; kalibracija regulacionih sipki; merenje viska reaktivnosti sa promenom visine nivoa teske vode i promenom broja sipki; merenje periode reaktora za odredjenu promenu reaktivnosti; merenje temperaturnog koeficijenta za vodu; merenje apsolutnog fluksa.

RB Research nuclear reactor, 30 years of operation; Istrazivacki nuclearni reaktor RB, povodom 30 godina rada

Energy Technology Data Exchange (ETDEWEB)

Pesic, M; Stefanovic, D [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

1988-06-15

Paper describes utilization, modifications and changes of construction and control-safety systems done at the RB reactor during 30 years of operation. Experiments performed at the reactor are summarized, new reactor equipment is described and the future plans are shown. Rad prikazuje eksploataciju reaktora RB tokom 30 godina rada, modifikacije i izmene u konstruktivnim i upravljacko-sigurnosnim sistemima. Sumirani su eksperimenti izvedeni na njemu, prikazana je nova oprema i planovi za buduci rad.

RA Research reactor, Annual report 1971; Istrazivacki nuklearni reaktor RA - Izvestaj za 1971. godinu - Pogon i odrzavanje

Energy Technology Data Exchange (ETDEWEB)

Milosevic, D et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1971-12-15

effects. In the introduction of this report it has been emphasised that the decision makers should have in mind the negative effects of low budget on the reactor safe and reliable operation. For the sake of reactor, decision about the future operation and financing should be done as soon as possible, either to cease operation or continue with adequate financial support. [Serbo-Croat] Reaktor RA je u 1971. godini radio na nominalnoj snazi 190 dana i 50 dana na manjim snagama. Ukupni rad iznosio je 31606 MWh odnosno 5,3% vise od planiranog, sto je najvisa vrednost od kako je reaktor pusten u rad. Reaktor je koriscen za ozracivanja i eksperimente za 425 korisnika od cega 370 iz Instituta i 55 za korisnika izvan Instituta. Ovaj izvestaj sadrzi detaljne podatke o radu i eksperimentima koji su obavljani. Odstupanja od plana, odnosno veceg ostvarenog rada bilo je u junu i decembru usled posebnih zahteva korisnika. Ukupni broj prekida rada bio je manji od svih prethodnih godina, uglavnom zbog manjeg broja nestanka napona u vreme rada reaktora. U toku godine bilo je samo jedno sigurnosno zaustavljanje, ciji je uzrok bila pojava laznog signala opreme za zastitu reaktora. Nijednog duzeg prekida rada nije bilo zbog neispravnosti opreme. Kracih prekida bilo je usled kidanja spojki na potisnom cevovodu tehnicke vode, sto je bilo izazvano klizanjem zemljista u podrucju crpne stanice na Dunavu. Ukupna doza ozracivanja ljudstva bila je manja nego prethodnih godina. Nije bilo ni jednog akcidenta niti slucaja koji bi se mogao nazvati akcidentom. Dekontaminirano je znatno manje povrsina nego ranijih godina. Zakljuceno je da je uspesan rad reaktora u 1971. godini rezultat valjanog rada u prethodnim godinama. Medjutim usled jos nedefinisane politike u pogledu buduceg rada, odnosno neizvesnosti u vezi finansiranja, neki poslovi su obustavljeni. Tu spada proucavanje mogucnosti prelaska na koriscenje visokoobogacenog goriva sto bi povecalo korisni neutronski fluks i ucinilo reakor konkurentnim za

A review of calculation methods for fast and intermediate reactors; Expose des methodes pour le calcul de reacteurs a neutrons rapides et intermediaires; Obzor metodov rascheta reaktorov na promezhutochnykh i bystrykh nejtronakh; Estudio panoramico de los metodos de calculo de los reactores rapidos e intermedios

Energy Technology Data Exchange (ETDEWEB)

Marchuk, G I [Akademiya Nauk, Moskva, Union of Soviet Socialist Republics (Russian Federation)

1962-03-15

de ecuaciones fundamentales y conjugadas de la teoria de los multigrupos. Expone luego diversas aplicaciones de la teoria de la perturbacion a los problemas del calculo fisico del reactor. Examina los metodos numericos de resolucion de las ecuaciones fundamentales y conjugadas que expresan el funcionamiento del reactor sobre la base del metodo de los armonicos esfericos. Explica asimismo como se utiliza el metodo de las caracteristicas en la solucion de problemas relativos a la masa critica del reactor. Describe los metodos de calculo de los reactores con moderadores que contienen hidrogeno y, por fin, expone las bases de un modelo efectivo fundado en la teoria de un solo grupo, aplicable al reactor. (author) [Russian] Obsuzhdaetsya razvitie metodov rascheta yadernykh reaktorov na promezhutochnykh i bystrykh nejtronakh. Rassmatrivayuts ya razlichnye postanovki zadach fizicheskogo rascheta. Obsuzhdaetsya uchet rezonansnykh ehffektov. Vvodyatsya v rassmotrenie mnogogruppovy e sistemy 'osnovnykh i sopryazhennykh uravnenij. Daetsya razlichnoe primenenie teorii vozmushchenij k zadacham fizicheskogo rascheta reaktora. Rassmatrivayuts ya chislennye metody resheniya osnovnykh i sopryazhennykh uravnenij reaktora v priblizhenii metoda sfericheskikh garmonik. Daetsya primenenie metoda kharakteristik k resheniyu zadach na kriticheskuyu massu reaktora. Izlagayutsya metody rascheta reaktorov s vodorodsoderzhashchim i zamedlitelyami . Izlagayutsya osnovy ehffektivnoj odnogruppovoj modeli reaktora. (author)

RA reactor building and installations; Zgrada 'RA' i instalacije

Energy Technology Data Exchange (ETDEWEB)

Badrljica, R; Sanovic, V; Skoric, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1985-08-15

RA reactor building is made of reinforced concrete and bricks. It is closed facility with a limited number of controlled openings, doors and windows. The site of the building is 100 m above the sea level, 20 m above the mean Danube level and 8 m above the level of the neighbouring stream Mlaka. The building consists of three parts: central prismatic part, annex - surrounding the central part and the sanitary corridor. The biggest space is the reactor hall. In addition to the detailed description and drawings of the reactor building this documents includes design specifications of: electrical installation, water supply system, sewage system, ventilation and heating, gas and compressed air systems. A separate chapter is devoted to fire protection. Zgrada reaktora RA izgradjena je od armiranog betona i opeke, kao zatvoreni objekat ogranicenog broja kontolisanih otvora, sa ogranicenim brojem vrata i prozora. Plato na kojem je zgrada izgradjena nalazi se na 100 m nadmorske visine, na 20 m iznad srednjeg vodostaja Dunava i 8 m iznad nivoa obliznjeg potoka Mlaka. Zgrada se sastoji iz tri dela: sredisnjeg prizmaticnog dela, aneksa - prstenastog okvira sredisnog dela i sanitarnog propusnika. Pojedinacno najveci prostor zauzima reaktorska hala. Pored detaljnog opisa i plana zgrade, ovaj dokument sadrzi projekat elektricne instalacije, projekat vodovoda i kanalizacije, ventilacije i grejanja, instalacije gasa i komprimovanog vazduha. Posebno poglavlje posveceno je protivpozarnoj zastiti.

Research nuclear reactor RA - Annual Report 1997; Istrazivacki nuklearni reaktor RA - Izvestaj za 1997. godinu

Energy Technology Data Exchange (ETDEWEB)

Sotic, O [Vinca Institute of Nuclear Sciences, Beograd (Serbia and Montenegro)

1997-12-01

RA reactor is not in operation since 1984, activities related to revitalisation of the RA reactor started in 1986. The planned actions related to renewal of the reactor components were finished except for the most important action, related to exchange of complete reactor instrumentation which was delayed. Only 80% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the sanctions imposed to our country. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 42 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved. Research reactor RA Annual report for year 1997 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] Reaktor RA nije u pogonu od 1984, aktivnosti na revitalizaciji, rekostrukciji i modernizaciji reaktorski sistema zapocete su 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Do septembra 1991. godine isporuceno svega 80% od predvidjene kolicine. Od tada je svaka isporuka obustavljena, a razlog je privremena zabrana na sve isporuke opreme za Jugoslaviju usled sankcija uvedenih od strane organizacije Ujedinjenih nacija. Demontirana je postojeca instrumentacija. Kontrola i odrzavanje celopkupne opreme postrojenja, kao i remontni radovi izvrsavani su redovno i efikasno. Kontrola goriva od strane safeguard inspektora MAAE obavljana

Noncommutative quantum mechanics

Science.gov (United States)

Gamboa, J.; Loewe, M.; Rojas, J. C.

2001-09-01

A general noncommutative quantum mechanical system in a central potential V=V(r) in two dimensions is considered. The spectrum is bounded from below and, for large values of the anticommutative parameter θ, we find an explicit expression for the eigenvalues. In fact, any quantum mechanical system with these characteristics is equivalent to a commutative one in such a way that the interaction V(r) is replaced by V=V(HHO,Lz), where HHO is the Hamiltonian of the two-dimensional harmonic oscillator and Lz is the z component of the angular momentum. For other finite values of θ the model can be solved by using perturbation theory.

Annual report of the group for maintenance of electrical equipment; Godisnji izvestaj elektro grupe

Energy Technology Data Exchange (ETDEWEB)

Rajic, M [Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1965-12-15

This report includes detailed description of repairs and revisions of the electrical equipment of the RA reactor which were done according to the annual plan during the periods when reactor was not operated. Unplanned repairs are part of this report as well. [Serbo-Croat] Ovaj izvestaj sadrzi detaljan opis remontnih i revizionih radova na elektroopremi reaktora RA izvrsenih prema godisnjem planu u periodima kada reaktor nije radio. Vanplanski poslovi ukljucujuci popravke elektroopreme su takodje deo ovog izvestaja.

Operating Experience with the VERA Zero-Energy Fast Reactor; Fonctionnement du Reacteur VERA a Neutrons Rapides, de Puissance Zero; Opyt ehkspluatatsii reaktora VERA na bystrykh nejtronakh nulevoj moshchnosti; Experiencia Adquirida con el Reactor Rapido VERA de Potencia Nula

Energy Technology Data Exchange (ETDEWEB)

Weale, J. W.; McTaggart, M. H.; Goodfellow, H.; Paterson, W. J. [Atomic Weapons Research Establishment, Aldermaston (United Kingdom)

1964-02-15

, intensidad de la fuente neutronica, empleo de un acelerador para producir neutrones; velocidad de respuesta de los circuitos de seguridad y restricciones subsiguientes en lo que atafle a la velocidad con que se pueden unir las dos mitados; precauciones adicionales necesarias al utilizar plutonio como combustible; notas sobre la precision de las mediciones de reactividad y sobre las limitaciones practicas que afectan a otras mediciones relacionadas con la fisica de los reactores. (author) [Russian] Daetsja kratkoe opisanie konstrukcii reaktora na bystryh nejtronah nule- voj moshhnosti, sostojashhego iz dvuh odinakovyh chastej. Pri jetom osoboe vnimanie udeljaetsja tem chertam, kotorye opredeljajut praktichnost' i obespechivajut tochnost' izmerenij po fizi- ke reaktorov. Obsuzhdajutsja preimushhestva i nedostatki konstrukcii s ssylkoj na dvuhlet- nij opyt jekspluatacii reaktora. Rassmatrivajutsja sledujushhie temy:prisposoblennost' proekta i konstrkcii iz dvuh odinakovyh chastej dlja provedenija jeksperimental'nyh issle- dovanij; razmer i kachestvo obrabotki toplivnyh blokov i tochnost' razmeshhenija toplivnyh jelementov; vlijanie granichnyh neravnomernostej i geterogennosti struktury na tochnost' opredelenija kriticheskoj massy ''ideal'noj'' jekvivalentnoj sborki; vosproizvodimost' kri- ticheskogo uslovija posle demontirovanija sborki ili razdelenija dvuh chastej; izmenenie reak- tivnosti s razdeleniem chastej, v tom chisle vlijanie nesimmetrichnoj zagruzki;chuvstvitel'- nost' razlichnyh schetchikov, moshhnost' istochnika nejtronov, ispol'zovanie istochnika uskorennyh nejtronov; bystrota otvetnoj reakcii konturov avarijnoj zashhity i posledujushhie ogranichenija skorosti sobiranija chastej; dopolnitel'nye predupreditel'nye mery, neobho- dimye pri ispol'zovanii plutonija; primechanija otnositel'no tochnosti izmerenija reaktiv- nosti i otnositel'no prakticheskih ogranichenij, vlijajushhih na razlichnye drugie izmerenija po fizike reaktorov. (author)

Waste generated by the future decommissioning of the Magurele VVR-S Research Reactor

International Nuclear Information System (INIS)

Dragolici, F.; Turcanu, C.N.; Dragolici, A.C.

2001-01-01

Nuclear Research Reactor WWR-S from the National Institute of Research and Development for Physics and Nuclear Engineering 'Horia Hulubei', Bucharest-Magurele, was commissioned in July 1957 and it was shut down in December 1997. At the moment the reactor is in conservation state. During its operation this reactor worked at an average power of 2MW, almost 3216 h/year, producing a total thermal power of 230 x 10 3 MWh. No major modifications or improvements were made during the 40 years of operation to the essential parts of the reactor, respective to the primary cooling system, reactor vessel, active core and electronic devices. So, all components of the measure, control and protection systems are old, generally at the technical level of the 1950s, therefore a reason why in December 1997 the operation was ceased. At present, the reactor can be considered, by IAEA definition in the first stage (reactor shut down, but the vital functions are maintained and monitored). The survey is related to the second stage - restrictive use of the area. To develop a real decommissioning project, it was first necessary to evaluate the volume and the characteristics of the radioactive waste which will be generated. Radioactive waste generated during the decommissioning of Magurele WR-S research reactor may be classified as: Activated wastes (internal structures, horizontal channels and thermal column, biological shield); Contaminated wastes (primary circuit non-activated components, hot cells, some technological rooms as main hall, pumps room, radioactive material transfer areas, ventilation building and stack); Possibly contaminated materials from any area of reactor building and ventilation building. After 40 years of nuclear research activities, all such areas are suspected of contamination. The volume of wastes that will result from WWR-S Research Reactor decommissioning is summarized

m m m contreras turrubiartes

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. M M M CONTRERAS TURRUBIARTES. Articles written in Bulletin of Materials Science. Volume 40 Issue 6 October 2017 pp 1225-1230. Thickness and photocatalytic activity relation in TiO 2 :N films grown by atomic layer deposition with methylene-blue and E. coli bacteria.

Avaliação da função renal do idoso em duas horas

OpenAIRE

Benarab,Maria do Carmo B. Sammartino; Castiglia,Yara Marcondes Machado; Vianna,Pedro Thadeu Galvão; Braz,José Reinaldo Cerqueira

2005-01-01

JUSTIFICATIVA E OBJETIVOS: Os idosos têm diminuição progressiva da função renal e os hipertensos, maior risco de lesão renal adicional no intra-operatório. Avalia-se a função renal pela depuração da creatinina, com débito urinário de 24 horas, para diluir o erro de possível volume vesical residual (VVR). O objetivo deste trabalho foi avaliar a função renal pré-operatória de idosos hipertensos e não-hipertensos, com débito urinário de duas horas, utilizando aparelho de ultra-som portátil para ...

Operating Experience in Nuclear Power Plants with Boiling-Water Reactors; Experience acquise dans l'exploitation des reacteurs a eau bouillante; Opyt ehkspluatatsii kipyashchago reaktora; Experiencia adquirida con la explotacion de reactores de agua hirviente

Energy Technology Data Exchange (ETDEWEB)

Ascherl, R. J. [General Electric Company, San Jose, CA (United States)

1963-10-15

, ''Rejnish vestfalishes ehlektritsitetsverk und bajernverk'', Kal'-na-Majne, Zapadnaya Germaniya. Rabochaya kharakteristika kipyashchego reaktora atomnoj ehlektrostantsii pri obychnom rezhime raboty v kommunal'noj ehnergosisteme ochen' khoroshaya. Koehffitsient ispol'zovaniya i moshchnosti reaktora i ehlektrostantsii daet tverdoe osnovanie polagat', chto ehlektrostantsii s kipyashchimi reaktorami yavlyayutsya nadezhnymi s tochki zreniya ikh rabochej kharakteristiki. V techenie 1963 goda budut vvedeny v stroj chetyre dopolnitel'nye ehlektrostantsii s kipyashchimi reaktorami: atomnaya ehlektrostantsiya v Big Rok Pojnt, ''Kons'yumers pauehr kompani'', Sharl'vua, Michigan, atomnaya ehnergeticheskaya ustanovka v KHamboldt Bej, ''Pasifik gaz ehnd ehlektrik kompani'', Yurika, Kaliforniya, atomnaya ehlektrostantsiya v Garig'yano, Natsional'noe obshchestvo po atomnoj ehnergii, Skauri, Italiya,i Yaponskij demonstratsionnyj ehnergeticheskij reaktor. Yaponskij nauchno-issledovatel'skij institut po atomnoj ehnergii, Tokai-Mura, Yaponiya. Pusk i pervonachal'naya ehkspluatatsiya ehtikh ehlektrostantsij podtverzhdayut predpolozhenie o nadezhnosti ikh raboty, chto uzhe prodemonstrirovano atomnymi ehlektrostantsiyami v Drezdene, Kale i Vallesitose. Rabochaya kharakteristika atomnykh ehlektrostantsij v Drezdene, Kale i Vallesitose yavlyaetsya naglyadnym dokazatel'stvom stabil'nosti i bezopasnosti kipyashikh reaktorov. Krome togo, urovni radiatsii na samoj ehlektrostantsii i v okruzhayushchej srede znachitel'no nizhe predelov, ustanovlennykh litsenziyami na ehkspluatatsiyu. Podtverdilis' prostota i legkost' ehkspluatatsii kipyashchikh reaktorov. Kharakteristika kontrolya za nagruzkoj u kipyashchego reaktora s dvojnym tsiklom Drezdenskoj ehlektrostantsii okazalas' ochen' khoroshej. Krupnye i nebol'shie raboty po ukhodu i remontu mogut osushchestvlyat'sya obychnymi remontnymi gruppami bez vrednykh posledstvij ili bez limita vremeni, svyazannymi s soobrazheniyami radioaktivnogo oblucheniya. V

RA research reactor - properties and experimental capabilities; Istrazivacki reaktor RA - Tehnicke karakteristike i eksploatacione mogucnosti

Energy Technology Data Exchange (ETDEWEB)

Milosevic, M; Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1978-05-15

The brief survey of the Reactor RA exploitation experience, as well as the reactor equipment state, after 18 years of operation is presented. The results of efforts spent on reactor characteristics improvement in order to ensure safe and reliable reactor operation for next 15-20 years, are described. Prikazani su fragmenti iz eksploatacije reaktora kao i stanje opreme, posle 18 godina rada. Na kraju je dat prikaz sta je preduzeto i sta se preduzima da se poboljsaju karakteristike i poveca sigurnost i bezbednost rada za sledecih 15-20 godina.

Advantages of retrofitting high velocity separators to LWR turbines; experience in VVR NPP Loviisa

International Nuclear Information System (INIS)

Dueymes, E.; Peyrelongue, J.P.

1992-01-01

Erosion-corrosion by wet steam is a concern for VVER operators and also, in numerous LWR power plants of western technology. The backfitting of moisture separators at the HP Turbine outlets is a way to avoid maintenance costs, repairs, replacement of pipes or equipments. Installation of HVS at LOVIISA confirms that this device, whose installation work is reduced to a minimum, is able to remove quite all the water from the steam just a few meters downstream the HP cylinder. A long term operation can be expected for carbon steel equipments, even those previously damaged by erosion-corrosion. (authors). 6 figs., 2 tabs

Control of the integrity of the fuel elements and the 30 years old reactor tank at the Dalat nuclear research reactor

International Nuclear Information System (INIS)

Hien, P.D.; Binh, N.T.; Ngo, N.T.; Nang, N.T.; Phuong, T.T.; Khang, N.P.; Bac, V.T.

1992-01-01

The aluminum tank of the Dalat nuclear research reactor is three decades old. Recent underwater optical inspection has revealed a number of corrosion spots, causing a certain concern about its longevity. Concerning the fuel assemblies of the Russian type VVR-M2 a regular radioactivity monitoring of air and reactor coolant water has not observed so far any anomaly related to the leakage of fission products. However, with more than 11,000 operating hours at nominal power since 1984 some fuel assemblies are now approaching the last stage of their lifetime and early detection of fuel failure must be paid due attention. Appropriate measures have been taken to maintain as good as possible the parameters of the primary coolant water during reactor shut-down periods, especially in the stagnant zones of the pool. Routine low-level measurements of fission products allow the early detection of anomaly leakage of the whole core as minor as 0.03 mCi/h of Xe-135 released into the pool water. Accurate account of the pool water loss and replenishment ensures the detection of invisible water leakage through the aluminum tank as low as 10 liters/week. Results of corrosion products monitoring show a slight increasing trend of corrosion rate of the whole primary coolant system. However from these data it is hard to conclude about the development status of the corrosion observed optically in the reactor tank.(Authors)(4 Fig. 4 Tables)

Control of the integrity of the fuel elements and the 30-years old reactor tank at the Dalat nuclear research reactor

International Nuclear Information System (INIS)

Pham Zuy Hien; Nguyen Thanh Binh; Nguyen Trong Ngo; Nguyen Thi Nang; Tran Thu Phuong; Ngo Phu Khang; Vuong Thu Bac.

1992-01-01

The aluminum tank of the Dalat nuclear research reactor is three decades old. Recent underwater optical inspection has revealed a number of corrosion spots, causing a certain concern about its longevity. Concerning the fuel assemblies of the Russian type VVR-M2 a regular radioactivity monitoring of air and reactor coolant water has not observed so far any anomaly related to the leakage of fissio products. However, with more than 11,000 operating hours at nominal power since 1984 some fuel assemblies are now approaching the last stage of their lifetime and early detection of fuel failure must be paid due attention. Appropriate measures have been taken to maintain as good as possible the parameters of the primary coolant water during reactor shut-down periods, especially in the stagnant zones of the pool. Routine low-level measurements of fission products allow the early detection of anomal leakage of the whole core as minor as 0.03 mCi/h of Xe-135 released into the pool water. Accurate account of the pool water loss and replenishment ensures the detection of invisible water leakage through the aluminum tank as low as 10 liters/week. Results of corrosion products monitoring show a slight increasing trend of corrosion rate of the whole primary coolant system. However from these data it is hard to conclude about the development status of the corrosion observed optically in the reactor tank. (author). 4 refs, 4 tabs, 4 figs

Research nuclear reactor RA - Annual Report 1989; Istrazivacki nuklearni reaktor RA - Izvestaj za 1989. godinu

Energy Technology Data Exchange (ETDEWEB)

Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1989-12-15

Annual report concerning the project 'RA research nuclear reactor' for 1989, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1989. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3705/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjering RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

Research nuclear reactor RA - Annual Report 1990 with the comparative evaluation for the period 1986-1990; Istrazivacki nuklearni reaktor RA - Izvestaj za 1990. godinu uz uporedni pregled za period 1986 - 1990

Energy Technology Data Exchange (ETDEWEB)

Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1990-12-15

Annual report concerning the project 'RA research nuclear reactor' for 1990, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1990. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3705/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjjring RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

RA Research nuclear reactor - Annual report 1987; Istrazivacki nuklearni reaktor RA - Izvestaj o radu za 1987. godinu

Energy Technology Data Exchange (ETDEWEB)

NONE

1987-12-15

Annual report concerning the project 'RA research nuclear reactor' for 1987, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1987. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3509/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjjring RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

RA Research reactor, Annual report 1988; Istrazivacki nuklearni reaktor RA - Izvestaj za 1988. godinu

Energy Technology Data Exchange (ETDEWEB)

Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1988-12-15

Annual report concerning the project 'RA research nuclear reactor' for 1989, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1989. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3705/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjering RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

Avaliação da função renal do idoso em duas horas Evaluación de la función renal de ancianos en dos horas Two-hour evaluation of renal function in the elderly

Directory of Open Access Journals (Sweden)

Maria do Carmo B. Sammartino Benarab

2005-06-01

Full Text Available JUSTIFICATIVA E OBJETIVOS: Os idosos têm diminuição progressiva da função renal e os hipertensos, maior risco de lesão renal adicional no intra-operatório. Avalia-se a função renal pela depuração da creatinina, com débito urinário de 24 horas, para diluir o erro de possível volume vesical residual (VVR. O objetivo deste trabalho foi avaliar a função renal pré-operatória de idosos hipertensos e não-hipertensos, com débito urinário de duas horas, utilizando aparelho de ultra-som portátil para determinação do volume vesical residual. MÉTODO: Foram analisados 30 pacientes, distribuídos em dois grupos, Gn (15, idosos não-hipertensos, e Gh (15, idosos hipertensos, coletando-se urina durante 2 horas. Mediu-se o VVR com aparelho de ultra-som portátil. Analisaram-se os seguintes parâmetros: idade, sexo, estado físico, altura, peso, índice de massa corpórea, creatinina plasmática e urinária, sódio e potássio plasmáticos e urinários, osmolalidade plasmática e urinária, débito urinário, depuração da creatinina, osmolar e de água livre, excreção urinária e fracionária de sódio e potássio. Comparou-se a depuração estimada de creatinina com a depuração da creatinina. RESULTADOS: Os pacientes de Gn e Gh não apresentaram diferenças significativas quanto à maioria dos parâmetros estudados. Os idosos hipertensos apresentaram tendência a maior excreção fracionária de sódio e o potássio plasmático mostrou-se mais baixo nos hipertensos, porém com valores normais. A depuração estimada de creatinina correlacionou-se positivamente com a de creatinina apenas em Gn. CONCLUSÕES: Os pacientes hipertensos apresentaram potássio plasmático mais baixo e excretaram mais sódio, tendo ocorrido correspondência entre a depuração estimada de creatinina e a depuração da creatinina apenas para os pacientes do grupo dos não-hipertensos.JUSTIFICATIVA Y OBJETIVOS: Los ancianos tienen disminución progresiva de

RB reactor noise analysis; Analiza sumova reaktora RB

Energy Technology Data Exchange (ETDEWEB)

Petrovic, M; Velickovic, Lj; Markovic, V; Jovanovic, S [Institut za nuklearne nauke Boris Kidric, Vinca, Beograd (Yugoslavia)

1964-07-01

Statistical fluctuations of reactivity represent reactor noise. Analysis of reactor noise enables determining a series of reactor kinetic parameters. Fluctuations of power was measured by ionization chamber placed next to the tank of the RB reactor. The signal was digitized by an analog-digital converter. After calculation of the mean power, 3000 data obtained by sampling were analysed.

Conditioning of radioactive aluminium generated by the VVR-S Nuclear Reactor Decommissioning Laboratory Inactive Tests

International Nuclear Information System (INIS)

Nicu, M.; Ionascu, L.; Turcau, C.; Dragolici, F.; Rotarescu, G.

2015-01-01

Aluminium is a reactive amphoteric metal, readily forming a protective oxide layer on contact with air or water. However, as the oxides are amphoteric, aluminium is not resistant to corrosion in acidic and alkaline conditions, because the protective films dissolve. As a consequence radioactive waste containing bulk aluminium alloys can not be embedded in Ordinary Portland Cement (OPC). A potential encapsulating material for the radioactive aluminium is potassium magnesium phosphate (MKP). This paper presents the characterization results obtained from analyzing the potential magnesium phosphate formulations and assesses its potential to reduce the corrosion of aluminium. A series of experiments have been performed. The main conclusions of the paper are as follows. First, the pH values of magnesium phosphate formulation investigated increased gradually over the test duration, with pH measurement ranging from 8.1 - 9.1, indicating lower values compared with the reference composite OPC (pH ∼ 13). The reduction of pH is an important controlling factor for the corrosion of aluminium. Secondly, according to XRD, the hardened magnesium phosphate matrix is polycrystalline and the main reaction product of magnesium phosphate cement formulations was confirmed as MgKPO 4 -6H 2 O, which was found to dominate the crystalline phase composition. Thirdly, the compressive strengths obtained for magnesium phosphate matrices investigated are included in the accepted limits for the embedding matrix with cement (above 5 N/mm 2 ). And fourthly, the corrosion of metallic aluminium in magnesium phosphate matrix is markedly reduced in comparison with the composite OPC

Influence of the neutron flux shape on the value of absorbed neutron dose; Uticaj oblika neutronskog spektra na vrednost apsorbovane doze neutrona

Energy Technology Data Exchange (ETDEWEB)

Miric, I; Miric, P [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

1974-07-01

This paper deals with the study od specific doses dependence on the type and approximation procedures of neutron spectra. Values of specific dose rates (dose per neutron cm{sub 2}) were analysed for neutron spectra from RB reactor in Vinca, Crac facility in Valduc (France) and HPRR reactor in Oak Ridge (USA). Data used in this analysis were obtained by methods used in Harwell (AERE), Oak Ridge (ORNL), Chalk River (AECL), CEN de Cadarache (CEA) and in the Boris Kidric Institute (IBK). Specific absorbed neutron doses were determined for each of the estimated spectra and presented in the form of kerma/(n.cm{sup -2}) and rad/((n.cm{sup -2}) units. The obtained results have shown the influence of the flux approximation procedure on the values of conversion factors for obtaining neutron doses from neutron flux. U okviru ovog rada radjeno je na ispitivanju zavisnosti specificnih doza od vrste i nacina aproksimacije neutronskog spektra. U radu su analizirane vrednosti specificnih doza (doza po n.cm{sup -2}) za neutronske spektre koji se dobijaju oko sledecih nuklearnih postrojenja: reaktora RB u Vinci, postrojenja CRAC u Valduc-u (Francuska), reaktora HPRR u Oak Ridge-u (SAD). Za analizu su korisceni podaci dobijeni metodama koje se koriste u nuklearnim centrima Harwell (AERE), Oak Ridge-u (ORNL), Chalk River-u (AECL), CEN de Cadarache (CEA) i Institutu Boris Kidric (IBK). Za svaki procenjeni spektar odredjene su specificne apsorbovane doze neutrona izrazene u kerma/(n.cm{sup -2}) i rad/(n.cm{sup -2}) jedinicama. Dobijeni rezultati su pokazali koliko nacin aproksimacije spektra utice na vrednost konverzionih faktora koji sluze za prelazak sa fluksa na dozu neutrona (author)

Theoretical descriptions of novel triplet germylenes M1-Ge-M2-M3 (M1 = H, Li, Na, K; M2 = Be, Mg, Ca; M3 = H, F, Cl, Br).

Science.gov (United States)

Kassaee, Mohamad Zaman; Ashenagar, Samaneh

2018-02-06

In a quest to identify new ground-state triplet germylenes, the stabilities (singlet-triplet energy differences, ΔE S-T ) of 96 singlet (s) and triplet (t) M 1 -Ge-M 2 -M 3 species were compared and contrasted at the B3LYP/6-311++G**, QCISD(T)/6-311++G**, and CCSD(T)/6-311++G** levels of theory (M 1  = H, Li, Na, K; M 2  = Be, Mg, Ca; M 3  = H, F, Cl, Br). Interestingly, F-substituent triplet germylenes (M 3  = F) appear to be more stable and linear than the corresponding Cl- or Br-substituent triplet germylenes (M 3  = Cl or Br). Triplets with M 1  = K (i.e., the K-Ge-M 2 -M 3 series) seem to be more stable than the corresponding triplets with M 1  = H, Li, or Na. This can be attributed to the higher electropositivity of potassium. Triplet species with M 3  = Cl behave similarly to those with M 3  = Br. Conversely, triplets with M 3  = H show similar stabilities and linearities to those with M 3  = F. Singlet species of formulae K-Ge-Ca-Cl and K-Ge-Ca-Br form unexpected cyclic structures. Finally, the triplet germylenes M 1 -Ge-M 2 -M 3 become more stable as the electropositivities of the α-substituents (M 1 and M 2 ) and the electronegativity of the β-substituent (M 3 ) increase.

M2M Optimizations in Public Mobile Networks

NARCIS (Netherlands)

Norp, A.H.J.; Landais, B.

2012-01-01

Many M2M applications use public telecommunications networks to transfer data from M2M devices to an M2M server. These telecommunications networks will have to be adapted to cope with the traffic generated by the projected growth of M2M applications. In the near future, many more devices will be

A Survey on M2M Service Networks

Directory of Open Access Journals (Sweden)

Juhani Latvakoski

2014-11-01

Full Text Available The number of industrial applications relying on the Machine to Machine (M2M services exposed from physical world has been increasing in recent years. Such M2M services enable communication of devices with the core processes of companies. However, there is a big challenge related to complexity and to application-specific M2M systems called “vertical silos”. This paper focuses on reviewing the technologies of M2M service networks and discussing approaches from the perspectives of M2M information and services, M2M communication and M2M security. Finally, a discussion on technologies and approaches potentially enabling future autonomic M2M service networks are provided. According to our conclusions, it is seen that clear definition of the architectural principles is needed to solve the “vertical silo” problem and then, proceeding towards enabling autonomic capabilities for solving complexity problem appears feasible. Several areas of future research have been identified, e.g., autonomic information based services, optimization of communications with limited capability devices, real-time messaging, creation of trust and end to end security, adaptability, reliability, performance, interoperability, and maintenance.

RA Research reactor, Annual report 1969; Istrazivacki nuklearni reaktor RA - Izvestaj za 1969. godinu - Pogon i odrzavanje

Energy Technology Data Exchange (ETDEWEB)

Milosevic, D et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1969-12-15

years of operation as well as purification of heavy water. [Serbo-Croat] Reaktor RA je u 1969. godini radio na nominalnoj snazi 200 dana i 15 dana na manjim snagama. Ukupni rad iznosio je 31131 MWh odnosno 3.77% vise od planiranog. Reaktor je koriscen za ozracivanja i eksperimenta prema zahtevima 463 korisnika iz Instituta i 63 izvan Instituta. Ovaj izvestak sadrzi detaljne podatke o snazi na kojoj je reaktor radio tokom 1969. godine i o uradjenim eksperimentima. Zakljuceno je da je reaktor RA uspesno radio prema planu rada. Da nije bilo problema sa napajanjem elektricnom energijom tokom poslednja tri meseca i niskog vodostaja Dunava u septembru i oktobru protekle godine bila bi to najuspesnija godina od pustanja reaktora u pogon. Broj sigurnosnih zaustavljanja nije bio veci u odnosu na prethodne dve godine i pored poteskoca u poslednjem kvartalu. Osoblje je bilo izlozeno povecanim dozama zracenja usled tri incidenta. Jedan je bio raspadanje kenera sa srebrom (zbog duzeg stajanja u aktivnoj zoni), sto je uzrokovalo kontaminaciju radne platforme, tako da je fon porastao za 10 do 100 puta od normalnohg Druga dva slucaja su bila otkazivanje uredjaja za mesanje goriva u tehnoloskim kanalima. Zamena goriva je radjena cetiri puta u toku godine, utroseno je 499 svezih gorivnih elemenata. Primenjena je metoda mesanja svezih gorivnih elemenata sa koriscenim gorivnim elementima u gorivnom kanalu. Dekontaminacija povrsina bila je na nivou prethodnih godina i pored problema sa srebrom. Kako su sa reaktora tokom godine otisla dva saradnika sa visokom spremom broj ljudi je opao na neophodan minimum za pogon i odrzavanje reaktora. Navrsavajuci u ovoj godini deset godina rada moze se reci da su rad i stanje opreme na tehnicki solidnom nivou. Kako bi se posle deset godina rada izvrsila kontrola vaznih komponenti reaktora i obavila rekoncentracija teske vode, za 1970. godinu je planirano da se proizvodnja smanji na 25000 MWh, a baziran je na istim principima kao i planovi za prethodne

mIBG; La mIBG

Energy Technology Data Exchange (ETDEWEB)

Kraeber-Bodere, F.; Bodet-Milin, C.; Ansquer, C. [Hotel-Dieu de Nantes, Service de Medecine Nucleaire, 44 (France); Rousseau, C. [Centre Regional de Lutte Contre le Cancer Rene-Gauducheau, Service de Medecine Nucleaire, 44 - Nantes (France)

2004-08-01

mIBG is a norepinephrine functional analog with presynaptic adrenergic function used as molecular tracer for more than 20 years in Nuclear Oncology and in Cardiology. Organs can be classed in four groups, depending on the tracer's uptake mechanism: group 1: no uptake, group 2: non specific uptake, group 3: uptake in sympathetic nervous system with short retention and group 4: uptake in sympathetic nervous system with long-term retention. At cellular level, mIBG transport across the plasma membrane involves an active mechanism (uptake 1) and a passive diffusion (uptake 2). Intra-cellular becoming depends on the existence of secretory granules. In the absence of secretory granules, mIBG is stored in the cytoplasm and shows no inactivation by MAO. In the presence of secretory granules, mIBG is transported into secretory granules by an active monoamine transport protein (uptake 3), which catalyzes an amine/H{sup +} antiport. Alteration of mIBG biodistribution by parameters, such as circulating catecholamine in pheochromocytoma, hypoxia, tumoral histo-type and medication, should be considered in routine clinical applications. (authors)

Reactor Radiation Loops as Large Gamma Sources; Boucles d'irradiation des reacteurs nucleaires utilisees comme sources gamma intenses; Radiatsionnye kontury yadernykh reaktorov kak moshchnye gamma-istochniki; Empleo de circuitos de irradiacion de los reactores como fuentes gamma de gran intensidad

Energy Technology Data Exchange (ETDEWEB)

Ryabukhina, Yu. S.

1963-11-15

vybrany kontury na zhidkikh pri komnatnoj temperature splavakh indiya. Bylo izucheno povedenie dvukh ehvtekticheskikh splavov indiya po otnosheniyu k nekotorym konstruktivnym materialam, i v nachale 1960 g. byl zapushchen pervyj stendovyj indij-gallievyj kontur. V rezul'tate dal'nejshikh rabot byli zapushcheny model'nyj indij-galdievyj kontur s aktivnost'yu v obluchatele do {approx} 100 g. eh k v radiya pri reaktore IRT AN Gruzinskoj SSR i stendovyj indij-gallij-olovyannyj kontur v kanale reaktora IRT IAEH AN SSSR. Nakonets, v 1962 g. byl zapushen rabochij indij-gallij-olovyannyj kontur pri reaktore IRT AN Latvijskoj SSR dlya provedeniya polupromyshlennykh radiatsionnykh protsessov. Maksimal'naya aktivnost' obluchatelya kontura 30 000 g. eh k v radiya. Doklad sostoit iz 4 razdelov: 1. Raschety radiatsionnykh konturov. Obobshchaetsya prodelannaya rabota po metodam rascheta radiatsionnykh konturov. 2. Model' radiatsionnogo indij-gallievogo kontura reaktora IRT-2000 v Tbilisi. Opisyvaetsya dejstvuyushchij kontur. 3. Indij-gallij-olovyannyj radiatsionnyj kontur yadernogo reaktora IRT AN Latvijskoj SSR. Opisyvaetsya dejstvuyushchij kontur. 4. Perspektivy dal'nejshego razvitiya radiatsionnykh konturov. Opisyvayutsya ehksperimenty, skhemy i privodyatsya raschety, na osnovanii kotorykh predstavlyaetsya vozmozhnym sozdanie konturov na tverdom margantse i mobil'nykh konturov na zhidkikh splavakh indiya. (author)

M1 and M2 Monocytes in Rheumatoid Arthritis: A Contribution of Imbalance of M1/M2 Monocytes to Osteoclastogenesis

Directory of Open Access Journals (Sweden)

Shoichi Fukui

2018-01-01

Full Text Available ObjectivesWe investigated the relationships among M1 monocytes, M2 monocytes, osteoclast (OC differentiation ability, and clinical characteristics in patients with rheumatoid arthritis (RA.MethodsPeripheral blood mononuclear cells (PBMCs were isolated from RA patients and healthy donors, and we then investigated the number of M1 monocytes or M2 monocytes by fluorescence-activated cell sorting. We also obtained and cultured CD14-positive cells from PBMCs from RA patients and healthy donors to investigate OC differentiation in vitro.ResultsForty RA patients and 20 healthy donors were included. Twenty-two patients (55% were anticitrullinated protein antibody (ACPA positive. The median M1/M2 ratio was 0.59 (0.31–1.11, interquartile range. There were no significant differences between the RA patients and healthy donors. There was a positive correlation between the M1/M2 ratio and the differentiated OC number in vitro in RA patients (ρ = 0.81, p < 0.001. The ACPA-positive patients had significantly higher M1/M2 ratios in vivo (p = 0.028 and significantly greater numbers of OCs in vitro (p = 0.005 than the ACPA-negative patients. Multivariable regression analysis revealed that the M1/M2 ratio was the sole significant contribution factor to in vitro osteoclastogenesis. RA patients with M1/M2 ratios >1 (having relatively more M1 monocytes had higher C-reactive protein and erythrocyte sedimentation rates than RA patients with M1/M2 ratios ≤1. M1-dominant monocytes in vitro produced higher concentrations of interleukin-6 upon stimulation with lipopolysaccharide than M2 monocytes.ConclusionM1/M2 monocytes imbalance strongly contributes to osteoclastogenesis of RA patients. Our findings cast M1 and M2 monocyte subsets in a new light as a new target of treatments for RA to prevent progression of osteoclastic bone destruction.

Calibration of RB reactor power; Kalibrisanje snage reaktora RB

Energy Technology Data Exchange (ETDEWEB)

Sotic, O; Markovic, H; Ninkovic, M; Strugar, P; Dimitrijevic, Z; Takac, S; Stefanovic, D; Kocic, A; Vranic, S [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

1976-09-15

The first and only calibration of RB reactor power was done in 1962, and the obtained calibration ratio was used irrespective of the lattice pitch and core configuration. Since the RB reactor is being prepared for operation at higher power levels it was indispensable to reexamine the calibration ratio, estimate its dependence on the lattice pitch, critical level of heavy water and thickness of the side reflector. It was necessary to verify the reliability of control and dosimetry instruments, and establish neutron and gamma dose dependence on reactor power. Two series of experiments were done in June 1976. First series was devoted to tests of control and dosimetry instrumentation and measurements of radiation in the RB reactor building dependent on reactor power. Second series covered measurement of thermal and epithermal neuron fluxes in the reactor core and calculation of reactor power. Four different reactor cores were chosen for these experiments. Reactor pitches were 8, 8{radical}2, and 16 cm with 40, 52 and 82 fuel channels containing 2% enriched fuel. Obtained results and analysis of these results are presented in this document with conclusions related to reactor safe operation.

RA Research reactor, Annual report 1973; Istrazivacki nuklearni reaktor RA - Izvestaj za 1973. godinu - Pogon i odrzavanje

Energy Technology Data Exchange (ETDEWEB)

Milosevic, D et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1973-12-15

podatke o radu i eksperimentima koji su obavljani. U toku godine bilo je 12 sigurnosnih zaustavljanja, od cega 7 zbog zbog elektricnog napona. Od tri zaustavljanja ciji je uzrok bila oprema, dva su bila zbog otkazivanja novih elektronskih cevi. Od dva zaustavljanja koja je izazvalo pogonsko osoblje, jedno je bilo usled nepazljivog ukljucivanja pomocnog potrosaca, a drugo je ucinio operator jer se cinilo da snaga reaktora naglo raste. Kracih prekida rada bilo je tri, usled najavljenog iskljucenja napona. Ukupna doza ozracivanja ljudstva bila je manja nego prethodnih godina. Nije bilo ni jednog akcidenta. Dekontaminirano je znatno manje povrsina nego ranijih godina, i sakupljeno manje otpada nego prethodnih godina, dok tecnih efluenata nije bilo. Zakljuceno je da uspesan rad reaktora u 1973. godini ima poseban znacaj kada se ima na umu kriza finansiranja izazvana neblagovremenim resavanjem statusa reaktora. Mnogi goruci problemi nisu reseni: kompletiranje rezervnih delova, zamena nekih elemenata opreme, zamena nekih instrumenata, i nabavka visokoobogacenog goriva.

A Survey on M2M Systems for mHealth: A Wireless Communications Perspective

Directory of Open Access Journals (Sweden)

Elli Kartsakli

2014-09-01

Full Text Available In the new era of connectivity, marked by the explosive number of wireless electronic devices and the need for smart and pervasive applications, Machine-to-Machine (M2M communications are an emerging technology that enables the seamless device interconnection without the need of human interaction. The use of M2M technology can bring to life a wide range of mHealth applications, with considerable benefits for both patients and healthcare providers. Many technological challenges have to be met, however, to ensure the widespread adoption of mHealth solutions in the future. In this context, we aim to provide a comprehensive survey on M2M systems for mHealth applications from a wireless communication perspective. An end-to-end holistic approach is adopted, focusing on different communication aspects of the M2M architecture. Hence, we first provide a systematic review ofWireless Body Area Networks (WBANs, which constitute the enabling technology at the patient’s side, and then discuss end-to-end solutions that involve the design and implementation of practical mHealth applications. We close the survey by identifying challenges and open research issues, thus paving the way for future research opportunities.

Role of Natural IgM Autoantibodies (IgM-NAA) and IgM Anti-Leukocyte Antibodies (IgM-ALA) in Regulating Inflammation.

Science.gov (United States)

Lobo, Peter I

2017-01-01

Natural IgM autoantibodies (IgM-NAA) are rapidly produced to inhibit pathogens and abrogate inflammation mediated by invading microorganisms and host neoantigens. IgM-NAA achieve this difficult task by being polyreactive with low binding affinity but with high avidity, characteristics that allow these antibodies to bind antigenic determinants shared by pathogens and neoantigens. Hence the same clones of natural IgM can bind and mask host neoantigens as well as inhibit microorganisms. In addition, IgM-NAA regulate the inflammatory response via mechanisms involving binding of IgM to apoptotic cells to enhance their removal and binding of IgM to live leukocytes to regulate their function. Secondly, we review how natural IgM prevents autoimmune disorders arising from pathogenic IgG autoantibodies as well as by autoreactive B and T cells that have escaped tolerance mechanisms. Thirdly, using IgM knockout mice, we show that regulatory B and T cells require IgM to effectively regulate inflammation mediated by innate, adaptive and autoimmune mechanisms. It is therefore not surprising why the host positively selects such autoreactive B1 cells that generate protective IgM-NAA, which are also evolutionarily conserved. Fourthly, we show that IgM anti-leukocyte autoantibodies (IgM-ALA) levels and their repertoire can vary in normal humans and disease states and this variation may partly explain the observed differences in the inflammatory response after infection, ischemic injury or after a transplant. Finally we also show how protective IgM-NAA can be rendered pathogenic under non-physiological conditions. IgM-NAA have therapeutic potential. Polyclonal IgM infusions can be used to abrogate ongoing inflammation. Additionally, inflammation arising after ischemic kidney injury, e.g., during high-risk elective cardiac surgery or after allograft transplantation, can be prevented by pre-emptively infusing polyclonal IgM, or DC pretreated ex vivo with IgM, or by increasing in vivo IgM

The M-Technologies in M-Learning

DEFF Research Database (Denmark)

Annan, Nana Kofi; Adjin, Daniel Michael Okwabi; Ofori-Dwumfour, George

2013-01-01

network are vivid examples of static-ICTs while smartphones, tablets and mini laptop with wireless network connectivity, represent mobile-ICTs. The purpose of this paper is to elucidate the relationship between mobile computing and communication technologies, and their implication for education delivery....... The phenomenon of using mobile-ICTs for teaching and learning as popularly refered to as m-learning and is an off-shoot of e-learning which implies the use of static-ICTs for learning. The problem however, is that m-learning has a highly fragmented meaning because most fail to understand all the constituents...... of m-learning which this paper perceives to be the interconnectivity between mobile device, mobile telecommunications and mobile applications in their entirety as inseparable elements of m-learning. The questions that this paper seeks to address are; what are the key technological components of m-learning...

Age of M92 and M15

International Nuclear Information System (INIS)

Sandage, A.

1983-01-01

Comparison of VandenBerg's isochrones for globular clusters with the photometry of many main-sequence stars in M92 and M15 gives an age of T = 18 +- 2 x 10 9 years for both clusters, using a vertical fit to the turn-off luminosity, together with distance modulii found from the period-color-luminosity relation of their RR Lyrae stars. Comparison of the systematics of the composite CM diagram for clusters of different metallicity with that predicted from VandenBerg's isochrones, all for T = 18 x 10 9 years, shows good agreement. Justification of the adopted zero-point value of M/sub v/ (RR,M92) = +0.63 is made by comparing the main sequences of M92, M3, and M5 with that defined by 11 field subdwarfs whose metallicities lie between [Fe/H] of -2.2 and -1.2 for which adequate astrometric distances exist

Attitude toward m-advertising and m-repurchase

Directory of Open Access Journals (Sweden)

Nadia Jiménez

2017-05-01

Full Text Available One of the business models that attracts scholars and professionals’ interest is mobile commerce. This paper applies the theory of shopping preference to this field. It analyzes the role of personal factors (perceived control and propensity to use technology, social factors (influence of a social group, and epistemic factors (compatibility to determine consumers’ attitude toward mobile advertising (m-advertising and mobile repurchase (m-repurchase. The information of 973 mobile shoppers is analyzed in two contexts (Spain as a developed country and Mexico as a developing country. A positive attitude toward m-advertising is confirmed to increase m-repurchase through the mobile phone and the indirect influence of personal, social, and epistemic factors on shoppers m-repurchase (through the attitude toward m-advertising varies depending on the analyzed market.

M2- and M5-branes in E11 current algebra formulation of M-theory

Science.gov (United States)

Shiba, Shotaro; Sugawara, Hirotaka

2018-03-01

Equations of motion for M2- and M5-branes are written down in the E11 current algebra formulation of M-theory. These branes correspond to currents of the second and the fifth rank antisymmetric tensors in the E11 representation, whereas the electric and magnetic fields (coupled to M2- and M5-branes) correspond to currents of the third and the sixth rank antisymmetric tensors, respectively. We show that these equations of motion have solutions in terms of the coordinates on M2- and M5-branes. We also discuss the geometric equations, and show that there are static solutions when M2- or M5-brane exists alone and also when M5-brane wraps around M2-brane. This situation is realized because our Einstein-like equation contains an extra term which can be interpreted as gravitational energy contributing to the curvature, thus avoiding the usual intersection rule.

Radiation protection at the RA Reactor in 1995, Part -2, Annex 2, Decontamination and actions, collection of liquid effluents and solid radioactive waste; Deo 2 - Prilog 2 - Dekontaminacija i intervencije, skupljanje tecnih efluenata i cvrstih radioaktivnih otpadnih materijala

Energy Technology Data Exchange (ETDEWEB)

Mandic, M; Vukovic, Z; Lazic, S; Plecas, I; Voko, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1995-12-01

Certain amount of solid waste results from RA reactor operation, the mean quantity of which depends on the duration of reactor operation and related activities. During repair, when reactor is not operated as well under accidental conditions, the quantity of waste is higher, dependent on the type of repair and comprehensiveness of decontamination of the working surface, contaminated tools and components. The waste is sorted and packed on the spot where they appeared according to the existing regulations and principles of radiation protection with aim to minimize unnecessary exposure of the radiation protection personnel who deals with control, transport, radioactive waste treatment and decontamination. During exceptional operations (decontamination, repair, bigger volume of contaminated material, etc.) professional staff of the Radiation protection department gives recommendations and helps in planning the actions related to repair, sorting and packaging of radioactive waste in special containers, identification of the contaminants, etc. [Serbo-Croat] Tokom rada reaktora RA dolazi do stvaranja odredjenih cvrstih otpadnih materijala cija prosecna kolicina zavisi od vremena rada reaktora i aktivnosti koje se tamo obavljaju. Tokom remonta, kada reaktor ne radi kao i pri akcidentalnim situacijama nastaju vece kolicine otpadnih materijala koje zavise od obima i vrste remontnih operacija i obima dekontaminacije kontaminirane radne povrsine i kontaminiranog alata, predmeta, opreme, itd. Nastali otpadni materijali se razvrstavaju i pakuju na mestu nastanka prema odgovarajucim propisima u skladu sa principima zastite od zracenja i aspekta bezbednosti u cilju minimiziranja nepotrebnog ozracivanja ljudstva za preuzimanje, kontrolu, transport, naknadnu obradu RAO i dekontaminaciju. Pri nerutinskim operacijama (dekontaminacija, remont, kontaminiarni otpadni materijal velike zapremine i sl.), strucna sluzba Institita ZASTITA pruza strucne konsultacije i pomaze pri planiranju

Contributions to the study of fast neutron spectrum in the 10 keV - 3 MeV range

International Nuclear Information System (INIS)

Garlea, I.

1979-01-01

The main objective of the work presented in this thesis was to create a fast neutron spectrum corresponding to the conditions required for a reference neutron field. The reference system for the fast neutron dosimetry in reactors, which the author promoted, is referred to as ΣΣ-ITN in the books. The conditions for introducing the ΣΣ systems into the thermal columns have been determined. The original contribution consists in determining the Westcott parameters of reactions 151 Eu(n,γ) 152 Eu and 176 Lu(n,γ) 17 +H7Lu used as thermal spectrum factors. The neutron description of the spectrum in cavity ΣΣ revealed that it is a Maxwell thermal spectrum displaying a temperature of 305+-7 deg C and a very small epithermal component (phisub(epi)/phisub(thermal) =4,5.10 -4 ). Better methods for determining reaction absolute rates resulted in less errors in calculating the microscopic integral sections mediated on the ΣΣ spectrum; there are under 5% errors for the fission cross sections and between 3% and 8% errors for the activating ones. The section values determined by the author have been included into the EXFOR library (IAEA); they are considered as reference measuremtns for the nuclear data improvement program. Testing the proposed method for the TRIGA on the ΣΣ-INT system proved that the multiple foil method provides correct results for both describing the spectral shape and for obtaining absolute values of the flux. Taking into account that the ΣΣ-ITN spectrum is a rapid one, the proposed method could not be tested within the low energy thermal and epithermal domain. For testing the method on an operational reactor, the core of the VVR-S IFIN reactor was employed. Due to the spectral structure of this reactor, it was possible to test the procedure within the whole energy range. In this view, the 5/10 core channel was selected which is similar to the channel required for measurements in the TRIGA-ROMANIA reactor. The absolute spectrum values are given in

Heat conductance of sintered UO{sub 2}; Toplotna provodljivost sinterovanog UO{sub 2}

Energy Technology Data Exchange (ETDEWEB)

Katanic-Popovic, J; Stevanovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

1966-11-15

Phenomena influencing the heat conductance of the sintered UO{sub 2} were analyzed, first of all when used as nuclear fuel. Influence of temperature, density and porosity, additives and irradiation in the reactor are shown. Based on the available literature, the measured heat conductance values were analyzed for the sintered UO{sub 2} outside the reactor and in the reactor during irradiation. Analizirane su pojave koje uticu na toplotnu provodljivost sinterovanog UO{sub 2}, pre svega, sa aspekta njegove primene kao goriva. Izlozen je uticaj temperature, gustine i poroznosti, aditiva i ozracivanja u reaktoru. Na osnovu pregleda dostupne literature kriticki su prikazani rezultati merenja toplotne provodljivosti sinterovanog UO{sub 2} van reaktora i u reaktoru pri ozracivanju (author)

Thermal conductivity of the sintered UO{sub 2}; Toplotna provodljivost sinterovanog UO{sub 2}

Energy Technology Data Exchange (ETDEWEB)

Katanic-Popovic, J; Stevanovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1967-04-15

Phenomena influencing the thermal conductivity of the sintered UO{sub 2} fuel were analyzed. Influence of temperature, density and porosity, additives and irradiation in the reactor core are presented. Thermal conductivity of sintered UO{sub 2} was measured both outside the reactor and during the irradiation in the reactor. Results are discussed and analyzed based on the available literature. Analizirane su pojave koje uticu na toplotnu provodljivost sinterovanog UO{sub 2}, pre svega, sa aspekta njegove primene kao goriva. Izlozen je uticaj temperature, gustine i poroznosti, aditiva i ozracivanja u reaktoru. Na osnovu pregleda dostupne literature kriticki su prikazani rezultati merenja toplotne provodljivosti sinterovanog UO{sub 2} van reaktora i u reaktoru pri ozracivanju (author)

El método de máximos y mínimos de Fermat

OpenAIRE

Alarcón, Sergio; Suescún, Carlos Mario

2004-01-01

El propósito de este trabajo es hacer un estudio detallado de la forma como Fermat explica en el Methodus su método de máximos y mínimos y, mostrar la falta de base de las anacrónicas interpretaciones que han dado algunos estudiosos de su método.

Apolipoprotein M

Directory of Open Access Journals (Sweden)

Nilsson-Ehle Peter

2004-10-01

Full Text Available Abstract Apolipoprotein M (apoM is a 26-kDa protein that is mainly associated with high-density lipoprotein (HDL in human plasma, with a small proportion present in triglyceride-rich lipoproteins (TGRLP and low-density lipoproteins (LDL. Human apoM gene is located in p21.31 on chromosome 6 (chromosome 17, in mouse. Human apoM cDNA (734 base pairs encodes 188-amino acid residue-long protein. It belongs to lipocalin protein superfamily. Human tissue expression array study indicates that apoM is only expressed in liver and in kidney and small amounts are found in fetal liver and kidney. In situ apoM mRNA hybridization demonstrates that apoM is exclusively expressed in the hepatocytes and in the tubule epithelial cells in kidney. Expression of apoM could be regulated by platelet activating factor (PAF, transforming growth factors (TGF, insulin-like growth factor (IGF and leptin in vivo and/or in vitro. It has been demonstrated that apoM expression is dramatically decreased in apoA-I deficient mouse. Hepatocyte nuclear factor-1α (HNF-1α is an activator of apoM gene promoter. Deficiency of HNF-1α mouse shows lack of apoM expression. Mutations in HNF-1α (MODY3 have reduced serum apoM levels. Expression of apoM is significantly decreased in leptin deficient (ob/ob mouse or leptin receptor deficient (db/db mouse. ApoM concentration in plasma is positively correlated to leptin level in obese subjects. These may suggest that apoM is related to the initiation and progression of MODY3 and/or obesity.

Molecular clouds in M31 and M33

International Nuclear Information System (INIS)

Blitz, L.

1985-01-01

In order to determine the properties of the molecular clouds in nearby spiral galaxies, 49 H II regions in M31 and 6 H II regions in M33 were observed using the J = 1→0 transition of CO. Of these, 17 were detected in M31 and two in M33. For the CO detection in M31, = 0.14 K, = 12.5 km s -1 , and = 2.1 K km s -1 . The two detections in M33, which are toward the giant H II regions NGC 604 and NGC 595, are somewhat weaker than the mean values for clouds in M31, neither T(/sub R/ nor ΔV shows any gradient with galactic radius, but is a decreasing function of radius. The mean values of and are considerably larger than the values that would be obtained by extrapolating local giant molecular clouds to the distance of M31. It is suggested that most of the CO emission is from small clouds in the beam which overwhelm the emission from the giant molecular clouds. Some observational tests of this suggestion are proposed. Like the molecular clouds in the Milky Way, the giant molecular clouds in M31 appear to be tidally limited. In M33 the larger inclination angle would make the observed contribution from small molecular clouds less significant, which is consistent with the observations

FT-IR spectroscopic study on the hofmann-Td type complex: M(4-Phenylpyridine)2M'(CN)4 (M=Ni; M'=Cd)

International Nuclear Information System (INIS)

Parlak, C.

2005-01-01

New Hofmann-Td type complex in the form of M(4-Phenylpyridine) 2 M'(CN) 4 (M = Ni, M' = Cd) was prepared in powder form and its infrared spectra is reported in the region of 4000-200 cm-1. From the spectral findings, this compound is similar in structure to the Hofmann-Td type complexes

Properties of M1-M2-Si-Al-O-N glasses (M1 = La or Nd, M2 = Y or Er)

Energy Technology Data Exchange (ETDEWEB)

Pomeroy, M.J.; Nestor, E.; Hampshire, S. [Limerick Univ. (Ireland). Materials and Surface Science Inst.; Ramesh, R. [Littelfuse Ireland, Dundalk, Co. Louth (Ireland)

2002-07-01

Mixed lanthanide cation oxynitride glasses have been prepared in the M1 - M2 - Si-Al-O-N systems where M1 = La or Nd and M2 = Y or Er. The densities ({rho}), Young's moduli (E), microhardnesses (H{sub v}), glass transition temperatures (T{sub g}), dilatometric softening temperatures (T{sub dil}) and coefficients of thermal expansion (CTE) of 13 glasses were determined. The molar volume values (MV) calculated from density data, E, H{sub v}, T{sub g}, T{sub dil} and CTE values were all found to vary linearly with the effective cation field strength arising from the M1 and M2 modifier cations. Least squares intercept and slope values are presented which correlate each property to effective cation field strength together with error values which arise from glass and specimen preparation and measurement inconsistencies. These linear correlations clearly indicate that the overall glass structure remains the same for each of the thirteen glasses with only the modifier cation(s) having any influence. This influence appears to be a cross-linking effect, the strength of which increases as the effective cation field strength of the M1, M2 modifiers increases. (orig.)

Structure and expression of MHC class Ib genes of the central M region in rat and mouse: M4, M5, and M6.

Science.gov (United States)

Lambracht-Washington, Doris; Moore, Yuki F; Wonigeit, Kurt; Lindahl, Kirsten Fischer

2008-04-01

The M region at the telomeric end of the murine major histocompatibility complex (MHC) contains class I genes that are highly conserved in rat and mouse. We have sequenced a cosmid clone of the LEW rat strain (RT1 haplotype) containing three class I genes, RT1.M6-1, RT1.M4, and RT1.M5. The sequences of allelic genes of the BN strain (RT1n haplotype) were obtained either from cDNAs or genomic clones. For the coding parts of the genes few differences were found between the two RT1 haplotypes. In LEW, however, only RT1.M5 and RT1.M6 have open reading frames; whereas in BN all three genes were intact. In line with the findings in BN, transcription was found for all three rat genes in several tissues from strain Sprague Dawley. Protein expression in transfectants could be demonstrated for RT1.M6-1 using the monoclonal antibody OX18. By sequencing of transcripts obtained by RT-PCR, a second, transcribed M6 gene, RT1.M6-2, was discovered, which maps next to RT1.M6-1 outside of the region covered by the cosmid. In addition, alternatively spliced forms for RT1.M5 and RT1.M6 were detected. Of the orthologous mouse genes, H2-M4, H2-M5, and H2-M6, only H2-M5 has an open reading frame. Other important differences between the corresponding parts of the M region of the two species are insertion of long LINE repeats, duplication of RT1.M6, and the inversion of RT1.M5 in the rat. This demonstrates substantial evolutionary dynamics in this region despite conservation of the class I gene sequences themselves.

Apolipoprotein M

DEFF Research Database (Denmark)

Christoffersen, Christina; Dahlbäck, B; Nielsen, L B

2006-01-01

ApoM is a novel apolipoprotein mainly present in high-density lipoprotein (HDL). It belongs to the lipocalin protein superfamily and may bind a small but so far unknown lipophilic ligand. It is secreted without cleavage of its hydrophobic signal peptide, which probably anchors apoM...... in the phospholipid moiety of plasma lipoproteins. Recent studies suggest that apoM may affect HDL metabolism and have anti-atherogenic functions. The subfraction of human HDL that contains apoM therefore protects LDL from oxidation and mediates cholesterol efflux more efficiently then HDL without apoM. In addition...... to hepatocytes, apoM is highly expressed in kidney proximal tubule cells. Recent data suggest that apoM is secreted into the pre-urine from the tubule cells but is normally taken up again in a megalin-dependent fashion. Further studies of mice with genetically modified apoM expression will be essential...

Towards Horizontal Architecture for Autonomic M2M Service Networks

Directory of Open Access Journals (Sweden)

Juhani Latvakoski

2014-05-01

Full Text Available Today, increasing number of industrial application cases rely on the Machine to Machine (M2M services exposed from physical devices. Such M2M services enable interaction of physical world with the core processes of company information systems. However, there are grand challenges related to complexity and “vertical silos” limiting the M2M market scale and interoperability. It is here expected that horizontal approach for the system architecture is required for solving these challenges. Therefore, a set of architectural principles and key enablers for the horizontal architecture have been specified in this work. A selected set of key enablers called as autonomic M2M manager, M2M service capabilities, M2M messaging system, M2M gateways towards energy constrained M2M asset devices and creation of trust to enable end-to-end security for M2M applications have been developed. The developed key enablers have been evaluated separately in different scenarios dealing with smart metering, car sharing and electric bike experiments. The evaluation results shows that the provided architectural principles, and developed key enablers establish a solid ground for future research and seem to enable communication between objects and applications, which are not initially been designed to communicate together. The aim as the next step in this research is to create a combined experimental system to evaluate the system interoperability and performance in a more detailed manner.

Tumor affinity of technetium-99m labeled radiopharmaceuticals. II. Sup(99m)Tc-Sn-diphosphonate (sup(99m)Tc-EHDP), sup(99m)Tc-Sn-dimercaptosuccinic acid (sup(99m)Tc-DMSA), sup(99m)Tc-Sn-diethyl stilbestrol diphosphate (sup(99m)Tc-DSDP)

Energy Technology Data Exchange (ETDEWEB)

Itoh, K; Kobayashi, S; Hisada, K; Tonami, N [Kanazawa Univ. (Japan). School of Medicine; Ando, A

1976-10-01

The authors have examined the tumor affinity of various sup(99m)Tc-labelled radiopharmaceuticals to Ehrlich's tumor for the purpose of delineating human malignant neoplasm positively. The biologic distributions of sup(99m)Tc-Sn-diphosphonate (sup(99m)Tc-EHDP), sup(99m)Tc-Sn-dimercaptosuccinic acid (sup(99m)Tc-DMSA) and sup(99m)Tc-Sn-diethyl stilbestrol diphosphate (sup(99m)Tc-DSDP, sup(99m)Tc-Honvan) are included as the second report on the tumor affinity of Ehrlich-bearing mice. Tumor concentration of sup(99m)Tc-EHDP was lowest and the positive delineation of implanted tumor with sup(99m)Tc-EHDP was poorest in sequential images, though active accumulation in some soft tissues malignant neoplasms, breast cancer, and thyroid cancer, has been reported. Tumor concentration and the tumor-to-blood ratio of sup(99m)Tc-DMSA were not so high, contrary to our expectation that /sup 197/Hg-DMSA might show high tumor concentration and high tumor-to-blood ratio the same as /sup 197/Hg chlormerodrin of the renal scanning radiopharmaceuticals. Tumor concentration of sup(99m)Tc-DSDP was highest. The tumor-to-blood concentration ratio was lower than that of the above mentioned radiopharmaceuticals but the tumor-to-liver ratio and/or tumor-to-lung ratio was over 1.0 at the earlier time. Biologic distribution of sup(99m)Tc-DSDP was similar to that of /sup 32/P labeled DSDP. It is presumed that sup(99m)Tc is labeled at the phosphate ester of DSDP which is dephospholytated immediately by phospholylase in vivo following intravenous injection. Although it is not known precisely it may be assumed that the mechanism of accumulating sup(99m)Tc-DSDP in Ehrlich's tumor is related to the phospholylase activity in neoplasms.

Design and Investigation of SST/nc-Si:H/M (M = Ag, Au, Ni and M/nc-Si:H/M Multifunctional Devices

Directory of Open Access Journals (Sweden)

A. F. Qasrawi

2013-01-01

Full Text Available Hydrogenated nanocrystalline Silicon thin films prepared by the very high frequency chemical vapor deposition technique (VHF-CVD on stainless steel (SST substrates are used to design Schottky point contact barriers for the purpose of solar energy conversion and passive electronic component applications. In this process, the contact performance between SST and M (M = Ag, Au, and Ni and between Ag, Au, and Ni electrodes was characterized by means of current-voltage, capacitance-voltage, and light intensity dependence of short circuit ( current and open circuit voltage ( of the contacts. Particularly, the devices ideality factors, barrier heights were evaluated by the Schottky method and compared to the Cheung's. Best Schottky device performance with lowest ideality factor suitable for electronic applications was observed in the SST/nc-Si:H/Ag structure. This device reflects a of 229 mV with an of 1.6 mA/cm2 under an illumination intensity of ~40 klux. On the other hand, the highest being 9.0 mA/cm2 and the of 53.1 mV were observed for Ni/nc-Si:H/Au structure. As these voltages represent the maximum biasing voltage for some of the designed devices, the SST/nc-Si:H/M and M/nc-Si:H/M can be regarded as multifunctional self-energy that provided electronic devices suitable for active or passive applications.

m6A-Driver: Identifying Context-Specific mRNA m6A Methylation-Driven Gene Interaction Networks

OpenAIRE

Zhang, Song-Yao; Zhang, Shao-Wu; Liu, Lian; Meng, Jia; Huang, Yufei

2016-01-01

As the most prevalent mammalian mRNA epigenetic modification, N6-methyladenosine (m6A) has been shown to possess important post-transcriptional regulatory functions. However, the regulatory mechanisms and functional circuits of m6A are still largely elusive. To help unveil the regulatory circuitry mediated by mRNA m6A methylation, we develop here m6A-Driver, an algorithm for predicting m6A-driven genes and associated networks, whose functional interactions are likely to be actively modulated ...

Current status of operation and utilization of the Dalat Research Reactor

International Nuclear Information System (INIS)

Nguyen Nhi Dien

2006-01-01

The Dalat Nuclear Research Reactor (DNRR) is a 500 kW pool-type reactor using the Soviet VVR-M2 fuel assembly with 36% enrichment of U-235. It was renovated and upgraded from the USA 250 kW TRIGA Mark-II reactor. The first criticality of the renovated reactor was in November 1983 and its regular operation at nominal power of 500 kW has been since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs, once every 4 weeks, for radioisotope production, neutron activation analysis, scientific research and training. The remaining time between two continuous runs is devoted to maintenance activities and also to short run for reactor physics and thermal hydraulics experiments. From the first start-up to the end of December 2003, it totaled about 26,000 hrs of operation and the total energy released was about 515 MWd. After 10 years of operation with the core of 89-fuel assembly configuration, in April 1994, the first refueling work was done and the 100-fuel assembly configuration was set-up. The second fuel reloading was executed in March 2002. At present time, the working configuration of the reactor core consists of 104 fuel assemblies. The next fuel reloading has been planned at the end of 2004. The current status of operation and utilization of the DNRR is presented and discussed in this paper. (author)

A candidate subspecies discrimination system involving a vomeronasal receptor gene with different alleles fixed in M. m. domesticus and M. m. musculus.

Directory of Open Access Journals (Sweden)

Robert C Karn

2010-09-01

Full Text Available Assortative mating, a potentially efficient prezygotic reproductive barrier, may prevent loss of genetic potential by avoiding the production of unfit hybrids (i.e., because of hybrid infertility or hybrid breakdown that occur at regions of secondary contact between incipient species. In the case of the mouse hybrid zone, where two subspecies of Mus musculus (M. m. domesticus and M. m. musculus meet and exchange genes to a limited extent, assortative mating requires a means of subspecies recognition. We based the work reported here on the hypothesis that, if there is a pheromone sufficiently diverged between M. m. domesticus and M. m. musculus to mediate subspecies recognition, then that process must also require a specific receptor(s, also sufficiently diverged between the subspecies, to receive the signal and elicit an assortative mating response. We studied the mouse V1R genes, which encode a large family of receptors in the vomeronasal organ (VNO, by screening Perlegen SNP data and identified one, Vmn1r67, with 24 fixed SNP differences most of which (15/24 are nonsynonymous nucleotide substitutions between M. m. domesticus and M. m. musculus. We observed substantial linkage disequilibrium (LD between Vmn1r67 and Abpa27, a mouse salivary androgen-binding protein gene that encodes a proteinaceous pheromone (ABP capable of mediating assortative mating, perhaps in conjunction with its bound small lipophilic ligand. The LD we observed is likely a case of association rather than residual physical linkage from a very recent selective sweep, because an intervening gene, Vmn1r71, shows significant intra(subspecific polymorphism but no inter(subspecific divergence in its nucleotide sequence. We discuss alternative explanations of these observations, for example that Abpa27 and Vmn1r67 are coevolving as signal and receptor to reinforce subspecies hybridization barriers or that the unusually divergent Vmn1r67 allele was not a product of fast positive

Decommissioning of evaporation technology for processing liquid radioactive waste in UJV Rez, a. s

International Nuclear Information System (INIS)

Tous, M.; Otcovsky, T.; Podlaha, J.

2015-01-01

The UJV Rez, a. s. is the main leader in processing institutional radioactive waste (RAW) in the Czech Republic and the Waste Management Department has been established since the research reactor VVR-S (now LVR-15) was put in operation. Due to the large activities in nuclear research and engineering in the past, a big capacity of waste management technologies was needed. The low pressure compactor for volume reduction of solid RAW, as well as chemical pre-treatment technology of liquid RAW were installed and later the evaporation technology for effective processing the liquid RAW with the cementation and bituminization unit for final conditioning of concentrated liquid RAW were used. During the years of research reactor operation and research activities in UJV Rez, a. s. there were two installed evaporation technologies in row. After the latest evaporator lifetime, changes in liquid RAW production and together with higher decontamination factor requirements, this technology was decided to be decommissioned. The decommissioned evaporation technology was installed and put in operation in 1991. This technology was used for processing liquid aqueous RAW produced from internal research activities and of course for external producers and institutions (e.g. universities, medicine, research institutes, industry). The approved decommissioning plan was prepared and the licence for immediate decommissioning was obtained in 2012. Then the decommissioning project started. The preparing stages as dosimetric survey, expected material balance and of course initial decontamination activities were performed. Evaporation technology dismantling and processing the arising RAW were done by the internal staff of Waste Management Department. The total volume of produced RAW was 49,5 m 3 of RAW. The secondary liquid RAW (from decontamination) of amount 1,4 m 3 , contaminated sludge of amount 0,5 m 3 , solid RAW (construction steel) of amount 39,1 m 3 , solid compressible RAW (protective

A short comparison between mT2 and mCT

International Nuclear Information System (INIS)

Serna, Mario

2008-01-01

We compare m T2 with m CT ; both are kinematic variables designed to find relationships between masses of pair-produced new states with symmetric decay chains. We find that for massless visible particles m CT equals m T2 in a particular limit. We identify advantages and disadvantages to the use of each variable. Tovey's paper on m CT also introduced a powerful concept of extracting mass information from an analysis at intermediate stages of a symmetric decay chain. We suggest that m T2 is a better tool for performing this analysis than m CT due to m T2 's better properties under initial state radiation.

RA reactor operation and maintenance; Pogon i odrzavanje reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

1963-02-15

This volume includes the final report on RA reactor operation and utilization of the experimental facilities in 1962, detailed analysis of the system for heavy water distillation and calibration of the system for measuring the activity of the air.

Chemical dosimetry at the RA reactor; Hemijska dozimetrija reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Gal, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1961-12-15

This report presents the results of measurements of absorbed doses axial and radial distribution in the vertical experimental channels of the RA reactor. Measurements were done in channels VK-5, VK-7, VK-9 and GF-36. Results were compared to the results of calorimetry measurements and measured neutron flux values performed by other laboratories. Fricke and oxalate dosemeters were used in addition to the cobalt indicators.

Oscillation characteristics of the reactor 'A'; Oscilatorne karakteristike reaktora 'A'

Energy Technology Data Exchange (ETDEWEB)

Zecevic, V; Lolic, B [The Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

1961-07-01

In addition to good knowledge of reactor physical properties, design of the reactor oscillator demands determining of the oscillator operating points as well as oscillation reactor properties. This paper contains study of the RA reactor power changes due to oscillations in in one of the vertical experimental channels. It has been concluded that the reactor optimum operating conditions are attained when the oscillator operates at optimum points, and other parameters are determined dependent on the sensitivity of the method and reactor stability.

Dosimetry system of the RB reactor; Dozimetarski sistem reaktora RB

Energy Technology Data Exchange (ETDEWEB)

Lolic, B; Vukadin, D [Boris Kidric Institute of nuclear sciences, Vinca, Belgrade (Yugoslavia)

1962-07-01

Although RB reactor is operated at very low power levels, safety and dosimetry systems have high importance. This paper shows detailed dosimetry system with fundamental typical components. Estimated radiation doses dependent on reactor power are given at some characteristic points in the rooms nearby reactor.

Absolute spectrophotometry in M31 and M32

International Nuclear Information System (INIS)

Oke, J.B.; Schwarzschild, M.

1975-01-01

For a number of places in the bulge of M31, and for two places in M32, photometric scans from lambda=3300 A to lambda=10,600 A have been obtained with the multichannel spectrometer on the 5-m Hale telescope. The scans show that in both objects the color temperature (particulary shortward of 5000 A) decreases toward the center, and that the strength of the CN bands increases toward the center in both objects, in agreement with other, earlier observations. The new data can all be interpreted in terms of an increase of heavy-element abundance toward the center in both objects by a factor probably less than 2, and by an excess of heavy elements in M31 compard with M32 by a factor probably greater than 2, in qualitative agreement with earlier conclusions of other observers

Observations of M dwarfs beyond 2.2 μm

International Nuclear Information System (INIS)

Berriman, G.

1987-01-01

This paper presents the first systematic spectroscopic observations of M dwarfs beyond 2.2μm. The coolest dwarfs show strong water absorption in the 3μm window, and beyond 4μm, the energy distributions of all the stars fall slightly less steeply than the Rayleigh-Jeans tail of a blackbody. Spectra between 1 and 4μm are essential in deriving accurate luminosities of M dwarfs, and possibly in deriving accurate effective temperatures too. New values reported here are not in general well explained by theoretical models of hydrogen burning stars. This is especially true for those cooler than 3000K: in the HR diagram they lie closer to brown dwarfs, in contrast to recent results based only on photometry. (author)

M-aminophenyltrialkylstannane

International Nuclear Information System (INIS)

Kassis, A.I.; Khawli, L.A.

1990-01-01

M-Radiohalo-aniline is a stable intermediate for preparing biotin-m-radiohalo-anilide to be used as an imaging agent or therapeutic agent. The invention also contemplates m-aminophenyltrialkylstannane which can be radiohalogenated and linked to biotin. No Drawings

Investigation of the connection between surface water and underground water from mine Cacova-Ierii, using activable tracers

International Nuclear Information System (INIS)

Dinescu, L.; Domocos, V.; Craciun, St.

1985-01-01

Two tracers, indium in the form of In-EDTA complex and 82 Br were simultaneously used in mining hydrology studies. The water samples were passed through an ion exchange column retaining the other disturbing elements, such as Mn, Cl, Na, K etc. Indium was coprecipitated with bismuth hydroxide and determined by NAA. Ten samples of precipitate in plastic bags, wrapped in Al foil, and the standard were irradiated simultaneously for 20 minutes by 10 13 n/cm 2 s neutron flux in the VVR-S reactor, and measured immeadiately after irradiation. Measurements were performed with a Ge(Li) detector and ND-6620 data acquisition and processing system. Measuring time was 200 s. The desintegration correction was taken into account for concentration calculations. Bromine 82 was determined by ''in situ'' measurements with scintillation probe. The connection between surface water and underground Cacova-Ierii mine water was proved, and data regarding the velocity and circulation were obtained

Definition of task (Phase II) B, 'Leak testing'; Definicija zadatka (II faza) B, 'Ispitivanje hermeticnosti'

Energy Technology Data Exchange (ETDEWEB)

Pavicevic, M; Nikolic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1963-01-15

In order to ensure safe Ra reactor operation and fulfilling the conditions for performing irradiation experiments it was necessary to test and verify the leak tightness of the sample containers and thermocouples, as well as the irradiation capsule before it was placed in the VISA-2 channel. Leak testing of VISA-2 channel with capsules and thermocouples was done before and after it was built-in the reactor. [Serbo-Croat] U cilju bezbednosti i sigurnosti rada reaktora RA i ispunjavanja uslova ozracivanja izvrsena je provera hermeticnosti kenera sa uzorcima i termoparovima, kao i hermeticnost kapsule pre ugradjivanja kapsule u kanal VISA-2. Izvrseno je i ispitivanje hermeticnosti kanala VISA-2 sa kapsulama i termoparovima pre ugradjivanja u reaktor i posle montaze.

Determination of the tritium content in the reactor heavy water; Odredjivanje porasta kolicine tritijuma u reaktorskoj teskoj vodi

Energy Technology Data Exchange (ETDEWEB)

Ribnikar, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1963-01-15

Quantity of tritium was measured in the heavy water, in the heavy water vapour and radiolyzed deuterium from the helium cover gas of the RA reactor. It has been shown that isotopic equilibrium D{sub 2}O+DT{r_reversible}DTO+D{sub 2} exists and that it is catalyzed by irradiation. Small quantities of ammonium in the reactor cover gas are inhibiting the migration of tritium from the heavy water. Izmerena ja sadrzina tritijuma u tecnoj teskoj vodi, njenoj pari i radiolizovanom deuterijumu iz helijumske atmosfere reaktora RA. Pokazano je da postoji izotopska ravnoteza D{sub 2}O+DT{r_reversible}DTO+D{sub 2}, koja je katalizovana zracenjem. Male kolicine amonijaka reaktorske atmosfere deluju u smislu otezavanja migracije tritijuma iz teske vode (author)

Report ETSI M2M-14bis JTC March 2011 meeting

NARCIS (Netherlands)

Keesmaat, N.W.

2011-01-01

The ETSI Technical Committee (TC) M2M focuses on the development of a generic M2M architecture and underlying protocols suitable for a wide range of M2M environments. Whereas in the past effort has been put in the development of several use cases, the focus of this M2M 14bis meeting – held in Sophia

mHealth

OpenAIRE

Bradáč, Filip

2015-01-01

Bachelor thesis is focused on mHealth solutions and its implementations into specific spe-cialized center of IQ-pohyb. The aim of this thesis is to carry out research on motivation health prevention at higher uti-lization of mHealth solutions by interrogating interested respondents. Statically process these results and draw conclusions that helps me find mHealth soulutions implementable into center of IQ-pohyb appropriately. First I focused on analysis of mHealth term filed in Telemedicine wh...

m manjula

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. M MANJULA. Articles written in Bulletin of Materials Science. Volume 41 Issue 1 February 2018 pp 19. Elastic and thermodynamic properties of zirconium- and hafnium-doped Rh$_3$V intermetallic compounds: potential aerospace material · M MANJULA M SUNDARESWARI ...

Immunoglobulin M

DEFF Research Database (Denmark)

Pleass, Richard J; Moore, Shona C; Stevenson, Liz

2016-01-01

Immunoglobulin M (IgM) is an ancient antibody class that is found in all vertebrates, with the exception of coelacanths, and is indispensable in both innate and adaptive immunity. The equally ancient human malaria parasite, Plasmodium falciparum, formed an intimate relationship with IgM with whic...

A distributed approach for secure M2M communications

OpenAIRE

BEN SAIED , Yosra; OLIVEREAU , Alexis; LAURENT , Maryline

2012-01-01

International audience; A key establishment solution for heterogeneous Machine to Machine (M2M) communications is proposed. Decentralization in M2M environment leads to situations where highly resource-constrained nodes have to establish end-to-end secured contexts with powerful remote servers, which would normally be impossible because of the technological gap between these classes of devices. This paper proposes a novel collaborative session key exchange method, wherein a highly resource-co...

Sujecion de piezas durante las mediciones con M.M.C

Directory of Open Access Journals (Sweden)

Miguel Ángel Sellés Cantó

2012-08-01

Full Text Available This Coordinate Measuring Machines (C.M.M. has had an increasingly important role throughout history. We are talking to an enterprise-level quality control. A system that is being implemented in all companies, and has developed some tools to control a variety of parameters such as production stabilization.In this paper, we first set out an introduction to the use of C.M.M. as tools for quality control in SME's. Then we explore the importance of piece positioning and clamping before being measured in a C.M.M. We finally analyze four possible moorings, and deviations are obtained. These moorings are designed in order to place the same work piece in the four cases.Finally, the results obtained are compared and show which is the best way to put the part on the C.M.M.

Star Formation in M 33 (HerM33es)

Science.gov (United States)

Kramer, C.; Boquien, M.; Braine, J.; Buchbender, C.; Calzetti, D.; Gratier, P.; Mookerjea, B.; Relaño, M.; Verley, S.

2011-11-01

Within the key project "Herschel M 33 extended survey" (HerM33es), we are studying the physical and chemical processes driving star formation and galactic evolution in the nearby galaxy M 33, combining the study of local conditions affecting individual star formation with properties only becoming apparent on global scales. Here, we present recent results obtained by the HerM33es team. Combining Spitzer and Herschel data ranging from 3.6 μm to 500μm, along with H i, Hα, and GALEX UV data, we have studied the dust at high spatial resolutions of 150 pc, providing estimators of the total infrared (TIR) brightness and of the star formation rate. While the temperature of the warm dust at high brightness is driven by young massive stars, evolved stellar populations appear to drive the temperature of the cold dust. Plane-parallel models of photon dominated regions (PDRs) fail to reproduce fully the [C ii], [O i], and CO maps obtained in a first spectroscopic study of one 2' × 2' subregion of M 33, located on the inner, northern spiral arm and encompassing the H ii region BCLMP 302.

Enhancing mTOR-targeted cancer therapy by preventing mTOR/raptor inhibition-initiated, mTOR/rictor-independent Akt activation

OpenAIRE

Wang, Xuerong; Yue, Ping; Kim, Young Ae; Fu, Haian; Khuri, Fadlo R.; Sun, Shi-Yong

2008-01-01

It has been shown that mTOR inhibitors activate Akt while inhibiting mTOR signaling. However, the underlying mechanisms and the impact of the Akt activation on mTOR-targeted cancer therapy are unclear. The present work focused on addressing the role of mTOR/rictor in mTOR inhibitor-induced Akt activation and the impact of sustained Akt activation on mTOR-targeted cancer therapy. Thus, we have demonstrated that mTOR inhibitors increase Akt phosphorylation through a mechanism independent of mTO...

Wide aperture multipole magnets of the kinematic separator COMBAS. Correcting pair of multipole magnets M3M4 (M5M6) with compensation for higher order aberrations

International Nuclear Information System (INIS)

Artyukh, A.G.; Gridnev, G.F.; Teterev, Yu.G.

1999-01-01

The high-resolving large aperture separator COMBAS has been created and commissioned. The magneto-optical structure of the separator is based on the strong focusing principle. The separator consists of eight wide aperture multipole magnets M1-M8. The magnets M1, M2, M7, M8 forming the 1 st order optics together with some higher order optical corrections and M3-M6 being dedicated to higher order corrections of the chromatic and spherical aberrations at the intermediate and exit foci of the separator. The multipole correctors M3-M6 contain the dipolar, sextupole and octupole components in their magnetic field distributions. It was the use of the rectangular dipoles M3-M6 as carriers of sextupole and octupole field components that let achieve high values of the separator angular and momentum acceptances. Measurements of the magnetic field distributions in the median planes of the pairs of magnets M3M6 (M4M5) have been performed. These measurements allowed one to analyze the magnets manufacturing quality. Based on the analysis, shimming of pole pieces of the pair of magnets M3M6 have been done. Pole surface correcting coils for the magnets M4M5 have been foreseen to compensate for small deviations (within a few percents) of the 2 nd and 3 rd order field components from the design values, which are probable due to manufacturing errors in all the magnets M1-M8. The measured magnetic field distributions are supposed to be used for particle trajectory simulations throughout the entire separator

Infinitely many N=1 dualities from m+1−m=1

Energy Technology Data Exchange (ETDEWEB)

Agarwal, Prarit; Intriligator, Kenneth; Song, Jaewon [Department of Physics, University of California,San Diego, La Jolla, CA 92093 (United States)

2015-10-06

We discuss two infinite classes of 4d supersymmetric theories, T{sub N}{sup (m)} and U{sub N}{sup (m)}, labelled by an arbitrary non-negative integer, m. The T{sub N}{sup (m)} theory arises from the 6d, A{sub N−1} type N=(2,0) theory reduced on a 3-punctured sphere, with normal bundle given by line bundles of degree (m+1,−m); the m=0 case is the N=2 supersymmetric T{sub N} theory. The novelty is the negative-degree line bundle. The U{sub N}{sup (m)} theories likewise arise from the 6d N=(2,0) theory on a 4-punctured sphere, and can be regarded as gluing together two (partially Higgsed) T{sub N}{sup (m)} theories. The T{sub N}{sup (m)} and U{sub N}{sup (m)} theories can be represented, in various duality frames, as quiver gauge theories, built from T{sub N} components via gauging and nilpotent Higgsing. We analyze the RG flow of the U{sub N}{sup (m)} theories, and find that, for all integer m>0, they end up at the same IR SCFT as SU(N) SQCD with 2N flavors and quartic superpotential. The U{sub N}{sup (m)} theories can thus be regarded as an infinite set of UV completions, dual to SQCD with N{sub f}=2N{sub c}. The U{sub N}{sup (m)} duals have different duality frame quiver representations, with 2m+1 gauge nodes.

RA Research reactor Annual report 1982 - Part 1, Operation, maintenance and utilization of the RA reactor; Istrazivacki nuklearni reaktor RA - Deo 1 - Pogon, odrzavanje i eksploatacija nuklearnog reaktora RA u 1982. godini

Energy Technology Data Exchange (ETDEWEB)

Sotic, O; Martinc, R; Kozomara-Maic, S; Cupac, S; Radivojevic, J; Stamenkovic, D; Skoric, M; Miokovic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1982-12-15

outdated spare parts. Project concerning renewal of the reactor equipment was initiated during the past year according to the contract with the Soviet Atomenergoexport and IAEA which has planned to spend 1 000 000 of rubles for this project. [Serbo-Croat] Probni rad reaktora zapocet septembra 1981. godine na snazi od 2 MW sa 80% obogacenim gorivom nastavljen je u celoj 1982. prema prethodno napravljenom planu. Pocetno jezgro formirano ja sa 44 gorivna kanala sa po deset gorivnih elemenata. Prva polovina godine iskoriscena je za neophodna merenja i ispitivanja radnih parametara rektora i funkcionisanje sistema i opreme u radnim uslovima. U drugoj polovini godine zapocet je program probnog rada na visim snagama. Utvrdjeno je da ugradjeni visak reaktivnosti i kapacitet kontrolnih sipki zadovoljava sigurnosne kriterijume MAAE, ugradjeni visak reaktivnosti moze da omoguci rad na snazi od 4,7 MW u 4 mesecne kampanje sa po 15-20 dana rada, postoje povoljni uslovi za hladjenje jezgra pri pocetnoj konfiguraciji. Izmeren je efekat pocetnog zatrovanja na reaktivnost i raspodelu snage, izmerena je pocetna prostorna raspodela neutronskog fluksa koja iznosi 3,9 10{sup 13} cm{sup -2} s{sup -1} pri znazi od 2 MW. Odredjena je promena kalibracionog koeficijenta u sistemu za automatsko odrzavanje snage. Svi rezultati ukazuju da ce pri nominalnoj snazi od 4,7 Mw biti zadovoljeni svi kriterijum sigurnosti i postovana ogranicenja u odnosu na koriscenje goriva. Po dobijanju dozvole za rad na punoj snazi morace da se izvrsi dopunski probni rad na snagama od 3, 4, i 4,7 MW. Prelaz od pocetne konfiguracije sa 44 gorivna kanala u jezgru vrsice se postupno da bi se dostigla ravnotezna konfiguracija sa 72 gorivna kanala sa po 10 elemenata. Reaktor nije radio u septembu mesecu zbog radova na zameni dela cevovoda koji povezuje pumpnu stanicu na Dunavu sa horizontalnim taloznikom. Kontrola i odrzavanje opreme izvrsavani su redovno u granicama raspolozivosti rezerbinh delova. Teskocu pricinjava

Tidal radii of the globular clusters M 5, M 12, M 13, M 15, M 53, NGC 5053 and NGC 5466 from automated star counts.

Science.gov (United States)

Lehmann, I.; Scholz, R.-D.

1997-04-01

We present new tidal radii for seven Galactic globular clusters using the method of automated star counts on Schmidt plates of the Tautenburg, Palomar and UK telescopes. The plates were fully scanned with the APM system in Cambridge (UK). Special account was given to a reliable background subtraction and the correction of crowding effects in the central cluster region. For the latter we used a new kind of crowding correction based on a statistical approach to the distribution of stellar images and the luminosity function of the cluster stars in the uncrowded area. The star counts were correlated with surface brightness profiles of different authors to obtain complete projected density profiles of the globular clusters. Fitting an empirical density law (King 1962) we derived the following structural parameters: tidal radius r_t_, core radius r_c_ and concentration parameter c. In the cases of NGC 5466, M 5, M 12, M 13 and M 15 we found an indication for a tidal tail around these objects (cf. Grillmair et al. 1995).

Holographic cosmology from a system of M2–M5 branes

International Nuclear Information System (INIS)

Sepehri, Alireza; Faizal, Mir; Setare, Mohammad Reza; Ali, Ahmed Farag

2016-01-01

In this paper, we analyze the holographic cosmology using a M2–M5 brane configuration. In this configuration, a M2-brane will be placed in between a M5-brane and an anti-M5-brane. The M2-brane will act as a channel for energy to flow from an anti-M5-brane to a M5-brane, and this will increase the degrees of freedom on the M5-brane causing inflation. The inflation will end when the M5-brane and anti-M5-brane get separated. However, at a later stage the distance between the M5-brane and the anti-M5-bran can reduce and this will cause the formation of tachyonic states. These tachyonic states will again open a bridge between the M5-branes and the anti-M5-branes, which will cause further acceleration of the universe.

Holographic cosmology from a system of M2–M5 branes

Energy Technology Data Exchange (ETDEWEB)

Sepehri, Alireza, E-mail: alireza.sepehri@uk.ac.ir [Faculty of Physics, Shahid Bahonar University, P.O. Box 76175, Kerman (Iran, Islamic Republic of); Research Institute for Astronomy and Astrophysics of Maragha (RIAAM), Maragha (Iran, Islamic Republic of); Faizal, Mir, E-mail: f2mir@uwaterloo.ca [Department of Physics and Astronomy, University of Waterloo, Waterloo, ON, N2L 3G1 (Canada); Setare, Mohammad Reza, E-mail: rezakord@ipm.ir [Department of Science, Campus of Bijar, University of Kurdistan, Bijar (Iran, Islamic Republic of); Ali, Ahmed Farag, E-mail: afali@fsu.edu [Department of Physics, Florida State University, Tallahassee, FL 32306 (United States); Department of Physics, Faculty of Science, Benha University, Benha 13518 (Egypt)

2016-05-15

In this paper, we analyze the holographic cosmology using a M2–M5 brane configuration. In this configuration, a M2-brane will be placed in between a M5-brane and an anti-M5-brane. The M2-brane will act as a channel for energy to flow from an anti-M5-brane to a M5-brane, and this will increase the degrees of freedom on the M5-brane causing inflation. The inflation will end when the M5-brane and anti-M5-brane get separated. However, at a later stage the distance between the M5-brane and the anti-M5-bran can reduce and this will cause the formation of tachyonic states. These tachyonic states will again open a bridge between the M5-branes and the anti-M5-branes, which will cause further acceleration of the universe.

Enhanced M1/M2 macrophage ratio promotes orthodontic root resorption.

Science.gov (United States)

He, D; Kou, X; Luo, Q; Yang, R; Liu, D; Wang, X; Song, Y; Cao, H; Zeng, M; Gan, Y; Zhou, Y

2015-01-01

Mechanical force-induced orthodontic root resorption is a major clinical challenge in orthodontic treatment. Macrophages play an important role in orthodontic root resorption, but the underlying mechanism remains unclear. In this study, we examined the mechanism by which the ratio of M1 to M2 macrophage polarization affects root resorption during orthodontic tooth movement. Root resorption occurred when nickel-titanium coil springs were applied on the upper first molars of rats for 3 to 14 d. Positively stained odontoclasts or osteoclasts with tartrate-resistant acid phosphatase were found in resorption areas. Meanwhile, M1-like macrophages positive for CD68 and inducible nitric oxide synthase (iNOS) persistently accumulated on the compression side of periodontal tissues. In addition, the expressions of the M1 activator interferon-γ and the M1-associated pro-inflammatory cytokine tumor necrosis factor (TNF)-α were upregulated on the compression side of periodontal tissues. When the coil springs were removed at the 14th day after orthodontic force application, root resorption was partially rescued. The number of CD68(+)CD163(+) M2-like macrophages gradually increased on the compression side of periodontal tissues. The levels of M2 activator interleukin (IL)-4 and the M2-associated anti-inflammatory cytokine IL-10 also increased. Systemic injection of the TNF-α inhibitor etanercept or IL-4 attenuated the severity of root resorption and decreased the ratio of M1 to M2 macrophages. These data imply that the balance between M1 and M2 macrophages affects orthodontic root resorption. Root resorption was aggravated by an enhanced M1/M2 ratio but was partially rescued by a reduced M1/M2 ratio. © International & American Associations for Dental Research 2014.

Influenza polymerase encoding mRNAs utilize atypical mRNA nuclear export.

Science.gov (United States)

Larsen, Sean; Bui, Steven; Perez, Veronica; Mohammad, Adeba; Medina-Ramirez, Hilario; Newcomb, Laura L

2014-08-28

Influenza is a segmented negative strand RNA virus. Each RNA segment is encapsulated by influenza nucleoprotein and bound by the viral RNA dependent RNA polymerase (RdRP) to form viral ribonucleoproteins responsible for RNA synthesis in the nucleus of the host cell. Influenza transcription results in spliced mRNAs (M2 and NS2), intron-containing mRNAs (M1 and NS1), and intron-less mRNAs (HA, NA, NP, PB1, PB2, and PA), all of which undergo nuclear export into the cytoplasm for translation. Most cellular mRNA nuclear export is Nxf1-mediated, while select mRNAs utilize Crm1. Here we inhibited Nxf1 and Crm1 nuclear export prior to infection with influenza A/Udorn/307/1972(H3N2) virus and analyzed influenza intron-less mRNAs using cellular fractionation and reverse transcription-quantitative polymerase chain reaction (RT-qPCR). We examined direct interaction between Nxf1 and influenza intron-less mRNAs using immuno purification of Nxf1 and RT-PCR of associated RNA. Inhibition of Nxf1 resulted in less influenza intron-less mRNA export into the cytoplasm for HA and NA influenza mRNAs in both human embryonic kidney cell line (293 T) and human lung adenocarcinoma epithelial cell line (A549). However, in 293 T cells no change was observed for mRNAs encoding the components of the viral ribonucleoproteins; NP, PA, PB1, and PB2, while in A549 cells, only PA, PB1, and PB2 mRNAs, encoding the RdRP, remained unaffected; NP mRNA was reduced in the cytoplasm. In A549 cells NP, NA, HA, mRNAs were found associated with Nxf1 but PA, PB1, and PB2 mRNAs were not. Crm1 inhibition also resulted in no significant difference in PA, PB1, and PB2 mRNA nuclear export. These results further confirm Nxf1-mediated nuclear export is functional during the influenza life cycle and hijacked for select influenza mRNA nuclear export. We reveal a cell type difference for Nxf1-mediated nuclear export of influenza NP mRNA, a reminder that cell type can influence molecular mechanisms. Importantly, we

Antibody responses of swine following infection with Mycoplasma hyopneumoniae, M. hyorhinis, M. hyosynoviae and M. flocculare.

Science.gov (United States)

Gomes Neto, João Carlos; Strait, Erin L; Raymond, Matthew; Ramirez, Alejandro; Minion, F Chris

2014-11-07

Several mycoplasma species possessing a range of virulence have been described in swine. The most commonly described are Mycoplasma hyopneumoniae, Mycoplasma hyorhinis, Mycoplasma hyosynoviae, and Mycoplasma flocculare. They are ubiquitious in many pig producing areas of the world, and except for M. hyopneumoniae, commercial antibody-based assays are lacking for most of these. Antibody cross-reactivity among these four mycoplasma species is not well characterized. Recently, the use of pen-based oral fluids for herd surveillance is of increasing interest. Thus, this study sought to measure pig antibody responses and the level of cross-reactivity in serum and pen-based oral fluids after challenge with four species of swine mycoplasmas. Four groups of four mycoplasma-free growing pigs were separately inoculated with the different mycoplasma species. Pen-based oral fluids and serum samples were collected weekly until necropsy. Species-specific Tween 20 ELISAs were used to measure antibody responses along with four other commercial M. hyopneumoniae ELISAs. Animals from all groups seroconverted to the challenge species of mycoplasma and no evidence of cross-contamination was observed. A delayed antibody response was seen with all but M. hyorhinis-infected pigs. Cross-reactive IgG responses were detected in M. hyopneumoniae- and M. flocculare-infected animals by the M. hyorhinis Tween 20 ELISA, while sera from M. hyosynoviae and M. flocculare-infected pigs were positive in one commercial assay. In pen-based oral fluids, specific anti-M. hyopneumoniae IgA responses were detected earlier after infection than serum IgG responses. In summary, while some antibody-based assays may have the potential for false positives, evidence of this was observed in the current study. Copyright © 2014 Elsevier B.V. All rights reserved.

) m /SrVO3 ( m = 5, 6) Superlattices

KAUST Repository

Dai, Qingqing

2018-05-04

The (LaV3+O3)m/SrV4+O3 (m = 5, 6) superlattices are investigated by first principles calculations. While bulk LaVO3 is a C‐type antiferromagnetic semiconductor and bulk SrVO3 is a paramagnetic metal, semiconducting A‐type antiferromagnetic states for both superlattices are found due to epitaxial strain. At the interfaces, however, the V spins couple antiferromagnetically for m = 5 and ferromagnetically for m = 6 (m‐dependence of the magnetization). Electronic reconstruction in form of charge ordering is predicted to occur with V3+ and V4+ states arranged in a checkerboard pattern on both sides of the SrO layer. As compared to bulk LaVO3, the presence of V4+ ions introduces in‐gap states that strongly reduce the bandgap and influence the orbital occupation and ordering.

The new 99mTc myocardial perfusion imaging agents: 99mTc-sestamibi and 99mTc-teboroxime

International Nuclear Information System (INIS)

Berman, D.S.; Kiat, H.; Maddahi, J.

1991-01-01

The two new 99m (99mTc) labeled myocardial perfusion agents, 99mTc-Sestamibi and 99mTc-Teboroxime, are now available for routine clinical application. Both agents allow assessment of ejection fraction by the first-pass technique at rest or during exercise, thus providing additional information not available with thallium-201. 99mTc-Sestamibi has long myocardial residence time, as well as adequate myocardial extraction, providing images of higher count density and superior quality compared with thallium-201. 99mTc-Teboroxime has excellent myocardial uptake characteristics but is cleared very rapidly from the myocardium. Both tracers have shown results similar to those obtained with thallium-201 for detection of coronary artery disease and the assessment of defect reversibility. 99mTc-Sestamibi studies using the rest/stress imaging sequence can be accomplished in approximately 5 hours; studies using dual-isotope imaging (rest thallium-201 and stress 99mTc-Sestamibi injection) can be completed in 1 to 2 hours. Gated stress images can be performed with 99mTc-Sestamibi, providing simultaneous information of myocardial perfusion at stress and resting wall motion or thickening and allowing rapid differentiation of ischemic from infarcted tissue. Because of its slow myocardial clearance and absence of redistribution, 99mTc-Sestamibi allows uncoupling of the time of injection from the time of imaging and thus can be valuable in the evaluation of acute myocardial infarction and outcome of thrombolytic therapy. With 99mTc-Teboroxime, rapid serial studies are feasible. Pharmacologic stress and rest studies with 99mTc-Teboroxime single photon emission computed tomography potentially can be completed in under 30 minutes. 73 references

I'm a Map, I'm a Green Tree

Science.gov (United States)

Anderson, Daniel

2010-01-01

I'm talking about the ways we represent ourselves and our world. I've put some thoughts on the topic together here--a gathering that enacts new media creating and takes up conceptual layers like metaphors, models, and composing. The primary sources are videos from the Get a Mac campaign, aka I'm a Mac; I'm a PC ads. Posthuman concepts blending…

Attitude toward m-advertising and m-repurchase

OpenAIRE

Jiménez Torres, Nadia Huitzilin; San Martín Gutiérrez, Sonia

2017-01-01

One of the business models that attracts scholars and professionals’ interest is mobile commerce. This paper applies the theory of shopping preference to this field. It analyzes the role of personal factors (perceived control and propensity to use technology), social factors (influence of a social group), and epistemic factors (compatibility) to determine consumers’ attitude toward mobile advertising (m-advertising) and mobile repurchase (m-repurchase). The information of 973 mobile shoppers ...

Clinical significance of LUNX mRNA, CK19 mRNA, CEA mRNA expression in detecting micrometastasis from lung cancer

International Nuclear Information System (INIS)

Zhu Guangying; Liu Delin; Chen Jie

2003-01-01

Objective: To evaluate the sensitivity, specificity and clinical significance of CK19 mRNA, CEA mRNA and LUNX mRNA for detecting micrometastasis by sampling the peripheral blood and regional lymph nodes of lung cancer patients. Methods: Reverse transcriptase chain reaction (RT-PCR) was used to detect LUNX mRNA, CK19 mRNA, CEA mRNA for micrometastasis by sampling the peripheral blood of 48 lung cancer patients and 44 regional lymph nodes of such patients treated by curative resection. Peripheral blood of 30 patients with pulmonary benign lesions and 10 normal healthy volunteers and lymph nodes of 6 patients with benign pulmonary diseases served as control. Results: 1) LUNX mRNA, CK19 mRNA, CEA mRNA were expressed in all (35/35) lung cancer tissues. 2) In the peripheral blood from 48 lung cancer patients, 30 (62.5%) were positive for LUNX mRNA, 24 (50.0%) positive for CK19 mRNA and 32(66.7%) positive for CEA mRNA. The positive detection rates of micrometastasis in 44 lymph nodes from lung cancer patients were 36.4% (16 out of 44) for LUNX mRNA, 27.3% (12 out of 44) for CK19 mRNA and 40.9% (18 out of 44) for CEA mRNA. 3) In the 30 blood samples from patients with pulmonary benign diseases, 2 (6.7%) expressed CK19 mRNA, but none expressed LUNX mRNA or CEA mRNA. All the 3 molecular markers were negative in the 10 blood samples from healthy volunteers. In 11 lymph nodes from patients with pulmonary benign lesions, none was positive for any of the three markers. 4) In 44 regional lymph nodes from lung cancer patients, 6 (13.6%) were positive for metastasis by histopathological examination, with a positive rate significantly lower than that of the RT-PCR (P<0.05). 5) The micrometastatic positive rate in the peripheral blood of 40 non-small cell lung cancer (NSCLC) patients was significantly related to TNM stage (P=0.01). Conclusions: LUNX mRNA, CK19 MRNA, CEA mRNA are all appropriate target genes for the detection of micrometastasis from lung cancer. LUNX mRNA and CEA m

) m /SrVO3 ( m = 5, 6) Superlattices

KAUST Repository

Dai, Qingqing; Lü ders, Ulrike; Fré sard, Raymond; Eckern, Ulrich; Schwingenschlö gl, Udo

2018-01-01

The (LaV3+O3)m/SrV4+O3 (m = 5, 6) superlattices are investigated by first principles calculations. While bulk LaVO3 is a C‐type antiferromagnetic semiconductor and bulk SrVO3 is a paramagnetic metal, semiconducting A‐type antiferromagnetic states

m-Health: Lessons Learned by m-Experiences

Science.gov (United States)

Bravo, José; Hervás, Ramón; González, Iván

2018-01-01

m-Health is an emerging area that is transforming how people take part in the control of their wellness condition. This vision is changing traditional health processes by discharging hospitals from the care of people. Important advantages of continuous monitoring can be reached but, in order to transform this vision into a reality, some factors need to be addressed. m-Health applications should be shared by patients and hospital staff to perform proper supervised health monitoring. Furthermore, the uses of smartphones for health purposes should be transformed to achieve the objectives of this vision. In this work, we analyze the m-Health features and lessons learned by the experiences of systems developed by MAmI Research Lab. We have focused on three main aspects: m-interaction, use of frameworks, and physical activity recognition. For the analysis of the previous aspects, we have developed some approaches to: (1) efficiently manage patient medical records for nursing and healthcare environments by introducing the NFC technology; (2) a framework to monitor vital signs, obesity and overweight levels, rehabilitation and frailty aspects by means of accelerometer-enabled smartphones and, finally; (3) a solution to analyze daily gait activity in the elderly, carrying a single inertial wearable close to the first thoracic vertebra. PMID:29762507

Podnikatelský záměr ve venkovském cestovním ruchu

OpenAIRE

Kohoutová, Ivana

2014-01-01

Diplomová práce se zabývá vypracováním podnikatelského záměru ve venkovském cestovním ruchu pro založení rodinného podniku. Tento podnik spojuje poskytování služeb v rámci rodinného venkovského penzionu s vlastní zemědělskou výrobou. Cílem práce je na základě provedených analýz, plánů a zhodnocení rizik, navrhnout podnikatelský plán sloužící jako nástroj pro rozhodování o jeho budoucí realizaci. The master's thesis deals with drawing up a rural tourism business plan for the establishment o...

Post-test analysis of components from selenide isotope generator modules M-7, M-15, and M-18

International Nuclear Information System (INIS)

Wei, G.C.; Keiser, J.R.; Crouse, R.S.; Allen, M.D.; Schaffhauser, A.C.

1979-05-01

Several critical components removed from SIG (Selenide Isotope Generator) thermoelectric modules M-7, M-15C, M-15D, and M-18 were examined. These modules failed to show the predicted stability and conversion efficiency. Understanding the degradation and identifying means for preventing it necessitated detailed post-test examinations of key parts in the modules. Steel springs, which provided pressure for contacts at the hot and cold ends of P- or N-legs, relaxed more than expected. Beryllium oxide insulators had dark deposits that caused electrical shorts. The GdSe 1 49 N-leg exhibited cracking. The (Cu,Ag) 2 Se P-leg lost weight or sublimed excessively in module M-7 and more than expected in the other modules

Characterization of mTOR-Responsive Truncated mRNAs in Cell Proliferation

Science.gov (United States)

2017-07-01

These findings identify a previously uncharacterized role for mTOR in modulating 3’- UTR length of mRNAs by alternative polyadenylation ( APA ). Another...outcome of APA in the mTOR-activated transcriptome is an early termination of mRNA transcription to produce truncated mRNAs with polyadenylation in...for exhaustive analysis of Alternative cleavage and polyadenylation ( APA ) events (Figure 1). In IntMAP, first the position of multiple

m-Commerce

OpenAIRE

VACKOVÁ, Kateřina

2013-01-01

The aim of this thesis was to suggest practical use of m-commerce in the company Elektra PV based on analysis of options of m-commerce in the Czech Republic and in the world. First part of this thesis investigates theoretical basics of mobile commerce. Next part processes three case studies about the companies Amazon, Argos and Alza.cz, then followed the analysis of m-commerce. Based on previous findings is suggested for the company Elektra PV to implement mobile application.

Possibilities of using metal uranium fuel in heavy water reactors; Mogucnosti upotrebe metalnog urana kao goriva za teskovodne reaktore

Energy Technology Data Exchange (ETDEWEB)

Djuric, B; Mihajlovic, A; Drobnjak, Dj [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

1965-11-15

There are serious economic reasons for using metal uranium in heavy water reactors, because of its high density, i.e. high conversion factor, and low cost of fuel elements production. Most important disadvantages are swelling at high burnup and corrosion risk. Some design concepts and application of improved uranium obtained by alloying are promising for achievement of satisfactory stability of metal uranium under reactor operation conditions. Postoje ozbiljni ekonomski razlozi za primenu metalnog urana u teskovodnim reaktorima, pre svega zbog njegove velike gustine, odnosno visokog konverzionog faktora, i zbog niskih troskova proizvodnje gorivnih elemenata. Glavne prepreke su bubrenje pri velikim stepenima sagorevanja i opasnost od korozije. Postoje veliki izgledi da se primenom odredjenih projektnih koncepcija i upotrebom legiranjem poboljsanog urana postigne zadovoljavajuca stabilnost metalnog urana u uslovima rada reaktora (author)

Nuclear-physical properties of 105,106m,110mAg

International Nuclear Information System (INIS)

Popov, Yu. S.; Zakharova, L. V.; Sadulin, V. V.; Andreev, O. I.; Pakhomov, A. N.

2005-01-01

The nuclear-physical properties of the nuclides 105,106m,110m Ag, which are concomitant nuclides in reactor production of 103 Pd and 109 Cd used in metrology of ionizing radiations and in nuclear medicine, were studied. The following quantities were determined by semiconductor X-ray and γ-ray spectrometry: the parameter K α /K β of X-ray K radiation accompanying the decay of 110m Ag and the intensities of γ-ray quanta with the energies of 280 and 345 keV ( 105 Ag); 430, 451, and 512 keV ( 106m Ag); 658, 764, 885, 938, and 1384 keV ( 110m Ag). The half-lives determined using the above γ-ray lines are as follows: T 1/2 ( 105 Ag) = 41.2 ± 0.1 days; T 1/2 ( 106m Ag) = 8.30 ± 0.07 days. The errors are given for 95% confidence level [ru

M-theory inflation from multi M5-brane dynamics

International Nuclear Information System (INIS)

Becker, Katrin; Becker, Melanie; Krause, Axel

2005-01-01

We derive inflation from M-theory on S 1 /Z 2 via the non-perturbative dynamics of N M5-branes. The open membrane instanton interactions between the M5-branes give rise to exponential potentials which are too steep for inflation individually but lead to inflation when combined together. The resulting type of inflation, known as assisted inflation, facilitates considerably the requirement of having all moduli, except the inflaton, stabilized at the beginning of inflation. During inflation the distances between the M5-branes, which correspond to the inflatons, grow until they reach the size of the S 1 /Z 2 orbifold. At this stage the M5-branes will reheat the universe by dissolving into the boundaries through small instanton transitions. Further flux and non-perturbative contributions become important at this late stage, bringing inflation to an end and stabilizing the moduli. We find that with moderate values for N, one obtains both a sufficient amount of e-foldings and the right size for the spectral index

V M Jali

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. V M Jali. Articles written in Bulletin of Materials Science. Volume 25 Issue 3 June 2002 pp 191-196 Thermal Properties. Synthesis and thermal expansion hysteresis of Ca1–SrZr4P6O24 · Basavaraj Angadi V M Jali M T Lagare N S Kini A M Umarji · More Details Abstract ...

Reliable Reporting for Massive M2M Communications with Periodic Resource Pooling

DEFF Research Database (Denmark)

Madueño, Germán Corrales; Stefanovic, Cedomir; Popovski, Petar

2014-01-01

This letter considers a wireless M2M communication scenario with a massive number of M2M devices. Each device needs to send its reports within a given deadline and with certain reliability, e.g., 99.99%. A pool of resources available to all M2M devices is periodically available for transmission...... to guarantee the desired reliability of the report delivery within the deadline. The fact that the pool of resources is used by a massive number of devices allows to base the dimensioning on the central limit theorem. The results are interpreted in the context of LTE, but they are applicable to any M2M...

Improved /sup 195m/Hg→/sup 195m/Au generator

International Nuclear Information System (INIS)

Panek, K.J.; Lindeyer, J.; van der Vlugt, H.C.

1985-01-01

The most recent state-of-the-art version of the /sup 195m/Hg→/sup 195m/Au generator is briefly discussed. Improvement of generator performance, particularly of elution yield, has been achieved by the introduction of columns containing a gradient-packed sorbent, by terminal sterilization of the columns in buffered sodium thiosulfate eluant, and by temperature variations during elutions. High loading of the generations (up to 450 mCi of /sup 195m/Hg) makes this generator usable for at least 3 days, even after longer (<24-hr) transportation times

Gentc99m, computational system for the technetium-99m generator

International Nuclear Information System (INIS)

Suparman, I.

1997-01-01

The technetium-99m generator is one of the main products of the PPR, as the continuity of the technetium-99m generator production is important for supporting the development of nuclear medicine. GENTC99M has been made for computational for the technetium-99m generator and includes data processing, documentation and information GENTC99M is also very useful in quality control application especially for the determinations of yield and radionuclidic impurities which consume much time. microsoft visual basic for MS-DOS and visual basic for windows have been used for making GENTC99M. Microsoft visual basic has several features that make it an ideal development language for both MS-DOS and Microsoft Windows. These features not only increase productivity, they also provide all the tools and hooks needed to develop some very sophisticated applications. for a production centre like PPR, GENTC99M is very useful to support the data processing, documentation and information system of the technetium-99m generator and it can also be modified for other products

Reliable Radio Access for Massive Machine-to-Machine (M2M) Communication

DEFF Research Database (Denmark)

Madueño, Germán Corrales

the service requirements can range from massive number of devices to ultra-reliable. This PhD thesis focuses on novel mechanisms to meet these requirements in a variety of wireless systems, from well-established technologies such as cellular networks, to emerging technologies like IEEE 802.11ah. Today...... an overwhelming 89% of the deployed M2M modules are GPRS-based. This motivates us to investigate the potential of GPRS as a dedicated M2M network. We show that by introducing minimal modifications to GPRS operation, a large number of devices can be reliably supported. Surprisingly, even though LTE is seen...... as the preferable solution for M2M, no mechanisms are in place to guarantee reliable M2M access. Contrary to mainstream solutions that focus on preventing overload, we introduce mechanisms to provide reliable M2M service. We also investigate what cellular networks can do about upcoming smart metering traffic...

Genetic diversity and differentiation of the Critically Endangered Hispaniolan palm Coccothrinax jimenezii M.M. Mejía & M.M. García based on novel SSR markers

Science.gov (United States)

The palm species Coccothrinax jimenezii M.M. Mejía & M.M. García is a Critically Endangered species (sensu IUCN) restricted to two populations from Haiti (one site on coastal areas near the city of Gonaïves with 43 individuals) and the Dominican Republic (one site on the shores of Lago Enriquillo ...

Quantitative comparison of PET performance—Siemens Biograph mCT and mMR

Energy Technology Data Exchange (ETDEWEB)

Karlberg, Anna M.; Sæther, Oddbjørn [Department of Radiology and Nuclear Medicine, St. Olavs Hospital, Olav Kyrres gt 17, 7006 Trondheim (Norway); Eikenes, Live [Department of Circulation and Medical Imaging, Norwegian University of Science and Technology, Postbox 8905, 7491 Trondheim (Norway); Goa, Pål Erik [Department of Radiology and Nuclear Medicine, St. Olavs Hospital, Olav Kyrres gt 17, 7006 Trondheim (Norway); Department of Physics, Norwegian University of Science and Technology, Trondheim (Norway)

2016-02-25

Integrated clinical whole-body PET/MR systems were introduced in 2010. In order to bring this technology into clinical usage, it is of great importance to compare the performance with the well-established PET/CT. The aim of this study was to evaluate PET performance, with focus on image quality, on Siemens Biograph mMR (PET/MR) and Siemens Biograph mCT (PET/CT). A direct quantitative comparison of the performance characteristics between the mMR and mCT system was performed according to National Electrical Manufacturers Association (NEMA) NU 2-2007 protocol. Spatial resolution, sensitivity, count rate and image quality were evaluated. The evaluation was supplemented with additional standardized uptake value (SUV) measurements. The spatial resolution was similar for the two systems. Average sensitivity was higher for the mMR (13.3 kcps/MBq) compared to the mCT system (10.0 kcps/MBq). Peak noise equivalent count rate (NECR) was slightly higher for the mMR (196 kcps @ 24.4 kBq/mL) compared to the mCT (186 kcps @ 30.1 kBq/mL). Scatter fractions in the clinical activity concentration range yielded lower values for the mCT (34.9 %) compared to those for the mMR (37.0 %). Best image quality of the systems resulted in approximately the same mean hot sphere contrast and a difference of 19 percentage points (pp) in mean cold contrast, in favour of the mCT. In general, point spread function (PSF) increased hot contrast and time of flight (TOF) increased both hot and cold contrast. Highest hot contrast for the smallest sphere (10 mm) was achieved with the combination of TOF and PSF on the mCT. Lung residual error was higher for the mMR (22 %) than that for the mCT (17 %), with no effect of PSF. With TOF, lung residual error was reduced to 8 % (mCT). SUV was accurate for both systems, but PSF caused overestimations for the 13-, 17- and 22-mm spheres. Both systems proved good performance characteristics, and the PET image quality of the mMR was close to that of the m

ARGUS laser plasma experiments at 1.06 μm, 0.53 μm and 0.35 μm

International Nuclear Information System (INIS)

Turner, R.E.; Campbell, E.M.; Mead, W.C.; Ze, F.; Max, C.; Phillion, D.W.; Lee, P.; Pruett, B.; Tirsell, G.; Lasinski, B.F.

1982-01-01

ARGUS wavelength scaling experiments have been performed on low (Be) and high (Au) Z disk targets, with laser wavelengths of 1.06 μm, 0.53 μm and 0.35 μm. The laser provided a 700 psec pulse, with up to 100J and 1.06 μm; 200J at 0.53 μm; and 40J at 0.35 μm. Laser intensities on target ranged from 3 x 10 13 to over 3 x 10 15 W/cm 2 , using an f/2.2 focusing system. Box calorimeter measurements show the expected increasing fractional absorption at shorter laser wavelengths; absolutely calibrated hard x-ray detectors show the number of suprathermal electrons to be greatly decreased. Scattered light measurements concentrated on stimulated Raman scattering, and the 3/2 harmonic. The SRS was spectrally and temporally resolved during 0.53 μm irradiations; our measurements showed the scattering to be principally from the convective instability, near tenth critical density. Near ω/2, a double peaked spectral feature is observed. The time resolved data show a number of interesting features, which are discussed

Distributed Energy-Efficient Topology Control Algorithm in Home M2M Networks

OpenAIRE

Lee, Chao-Yang; Yang, Chu-Sing

2012-01-01

Because machine-to-machine (M2M) technology enables machines to communicate with each other without human intervention, it could play a big role in sensor network systems. Through wireless sensor network (WSN) gateways, various information can be collected by sensors for M2M systems. For home M2M networks, this study proposes a distributed energy-efficient topology control algorithm for both topology construction and topology maintenance. Topology control is an effective method of enhancing e...

New GUT predictions for mτ/mb and mμ/ms

International Nuclear Information System (INIS)

Antusch, Stefan

2010-01-01

Group theoretical factors from GUT symmetry breaking can lead to predictions for the ratios of quark and lepton masses (or Yukawa couplings) at the unification scale. Due to supersymmetric (SUSY) threshold corrections the viability of such predictions can depend strongly on the SUSY parameters. For three common minimal SUSY breaking scenarios with anomaly, gauge and gravity mediation we discuss which GUT scale ratios m e /m d m μ /m s , y τ /y b and y t /y b are allowed when phenomenological constraints from electroweak precision observables, B physics, (g - 2) μ , mass-limits on sparticles from direct searches as well as, optionally, constraints from the observed dark matter density are taken into account. We derive possible new predictions for the GUT scale mass ratios and compare them with the phenomenologically allowed ranges. We find that new GUT scale predictions such as m μ /m s = 9/2 or 6 and y τ /y b = 3/2 or 2 are often favoured compared to the ubiquitous relations m μ /m s = 3 or y τ /y b = 1. The talk is based on the results obtained in Refs. [1, 2].

Hydrocoil Turbine Performance at 3 m, 4 m, and 5 m Head Analysis Using Computational Fluid Dynamics Method

Science.gov (United States)

Luthfie, A. A.; Pratiwi, S. E.; Hidayatulloh, P.

2018-03-01

Indonesia is a country which has abundant renewable energy resources, comprises of water, solar, geothermal, wind, bioenergy, and ocean energy. Utilization of water energy through MHP is widely applied in remote areas in Indonesia. This utilization requires a water-converting device known as a water turbine. Rosefsky (2010) developed a water turbine known as the Hydrocoil turbine. This turbine is an axial turbine which is a modification of screw turbine. This turbine has a pitch length that decreases in the direction of the water flow and is able to work at relatively low water flow and head. The use of Hydrocoil turbine has not been widely applied in Indonesia, therefore this research is focused on analyzing the performance of Hydrocoil turbine. The analysis was performed using Computational Fluid Dynamics (CFD) method. Hydrocoil turbine performance analysis was performed at 3 m, 4 m, and 5 m head respectively as well as rotational speed variations of 100 rpm, 300 rpm, 500 rpm, 700 rpm, 900 rpm, 1,100 rpm, 1,300 rpm, 1,500 rpm, 1,700 rpm, and 1,900 rpm. Based on simulation result, the largest power generated by the turbine at 3 m head is 1,134.06 W, while at 4 m and 5 m are 1,722.39 W and 2,231.49 W respectively. It is also found that the largest turbine’s efficiency at 3 m head is 93.22% while at 4 m and 5 m head are 94.6% and 89.88% respectively. The result also shows that the larger the head the greater the operational rotational speed range.

The Armys M-1 Abrams, M-2/M-3 Bradley, and M-1126 Stryker: Background and Issues for Congress

Science.gov (United States)

2016-04-05

the Army John McHugh , urging instead the limited production of 70 M-1A2SEPv2 tanks per year from FY2013 to FY2017. 32 Congress subsequently decided...House Members sent a letter to Secretary of the Army McHugh expressing concern over the Army’s failure to fund production of the M-1A2. Congress...John McHugh by Rep. Sander Levin and Rep. Mike Rogers, May 6, 2011. 33 See CRS Reports: CRS Report R43323, Defense: FY2014 Authorization and

M-commerce

DEFF Research Database (Denmark)

Ulhøi, John Parm; Jørgensen, Frances

2009-01-01

Når små og mellemstore virksomheder (SMVer [F1] ) vover sig ud i nye forretningsmuligheder, som baserer sig på mobile devices via trådløs kommunikation med et forretningsmæssigt formål for øje eller 'Mobile Commerce' (M-commerce), skal de være meget dygtige til både at udnytte forkantsteknologier...... af disse netværk som en central del af nye M-commerce forretningsmodeller for SMVer og at redegøre for de foreløbige resultater fra projektets indledende fase. Projektets formål er at udforske, beskrive og facilitere udviklingen af nye forretningsmodeller for M-commerce i danske SMVer. Data er blevet...... indsamlet gennem dybdeinterview. Artiklen bidrager til teori om M-commerce forretningsmodeller, og i særdeleshed, modeller der karakteriseres af intenst netværkssamarbejde.   [F1] Jeg er ikke overbevist, at vi ikke skulle bruge SMEs, da det er meget mere kendt, også herhjemme....

A proposal for M2-brane-anti-M2-brane action

International Nuclear Information System (INIS)

Garousi, Mohammad R.

2010-01-01

We propose a manifestly SO(8) invariant BF type Lagrangian for describing the dynamics of M2-brane-anti-M2-brane system in flat spacetime. When one of the scalars which satisfies a free-scalar equation takes a large expectation value, the M2-brane-anti-M2-brane action reduces to the tachyon DBI action of D2-brane-anti-D2-brane system in flat spacetime.

Mismatched uptake of Tc-99m-ECD and Tc-99m-HMPAO in subacute cerebral infarction: Tc-99m-ECD for viability and Tc-99m-HMPAO for flow restoration

Energy Technology Data Exchange (ETDEWEB)

Lee, D. S.; Hyun, I. Y.; Kim, S. K. [College of Medicine, Seoul National Univ., Seoul (Korea, Republic of)] [and others

1997-07-01

Tc-99m-HMPAO reflects tissue perfusion but Tc-99m-ECD uptake is affected by tissue viability in addition to tissue perfusion which the varied state of cellular retention of Tc-99m-ECD reflects. Luxuriously perfused area on Tc-99m-HMPAO SPECT implies that this cortex was already reperfused either spontaneously or after thrombolysis and that accompanied paralysis of vascular reactivity in those zones warms progressive deterioration. We tried to find out if we can use sequential Tc-99m-ECD/Tc-99m-HMPAO SPECT to reveal cortical perfusion and severity and range of risky areas of cerbral cortex despite reperfusion in sub-acute infarction. In 13 patients (M ; F =7 : 6, mean age 57 (range: 26-84)) with cortical (n=12) and basal ganglia infarction (1), we performed sequential Tc-99m-ECD/Tc-99m-HMPAO SPECT at the same position. At first, 555 MBq of Tc-99m-ECD was injected and imaged and then 1110 MBq of Tc-99m-HMPAO was injected again and imaged with the patients in situ, and the first image (Tc-99m-ECD) and the subtracted image (2nd- 1st : Tc-99m-HMPAO) were compared slice by slice. Study was done from 3 days to 31 days (16{+-}9) after ictus. Tc-99m-ECD uptake was always less than or equal to Tc-99m-HMPAO uptake at the lesion in all cases. Luxury perfusion was prominent in four patients. Mismatched uptake was found in 10 patients. Severity of mismatch showed diverse spectrum and was ranged from total middle cerebral artery territory (1 case) to peripheral thin zones around infarction (2 cases). The other 7 showed intermediate amount of tissues with mismatch , i.e., Tc-99m-ECD defects where Tc-99m-HMPAO uptake is in part increased, normal or decreased. Upon discharge, patients having more uptake with Tc-99m-ECD predicted improvement. Patients having mismatched uptake went dichotomous way. In conclusion, Tc-99m-ECD/Tc-99m-HMPAO sequential SPECT is feasible and reveal both tissue perfusion (Tc-99m-HMPAO ) and discrepant Tc-99m-ECD uptake probably reflecting viability in acute

77 FR 29692 - Segun M. Rasaki, M.D.; Decision and Order

Science.gov (United States)

2012-05-18

... CFR 1316.67. Dated: May 4, 2012. Michele M. Leonhart, Administrator. Paul E. Soeffing, Esq., for the... reinstatement.'' Stuart A. Bergman, M.D., 70 Fed. Reg. 33,193 (DEA 2005); Roger A. Rodriguez, M.D., 70 Fed. Reg...

RB research reactor safety report; Izvestaj o sigurnsti istrazivackog reaktora RB

Energy Technology Data Exchange (ETDEWEB)

Sotic, O; Pesic, M; Vranic, S [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

1979-04-15

This new version of the safety report is a revision of the safety report written in 1962 when the RB reactor started operation after reconstruction. The new safety report was needed because reactor systems and components have been improved and the administrative procedures were changed. the most important improvements and changes were concerned with the use of highly enriched fuel (80% enriched), construction of reactor converter outside the reactor vessel, improved control system by two measuring start-up channels, construction of system for heavy water leak detection, new inter phone connection between control room and other reactor rooms. This report includes description of reactor building with installations, rector vessel, reactor core, heavy water system, control system, safety system, dosimetry and alarm systems, experimental channels, neutron converter, reactor operation. Safety aspects contain analyses of accident reasons, method for preventing reactivity insertions, analyses of maximum hypothetical accidents for cores with natural uranium, 2% enriched and 80% enriched fuel elements. Influence of seismic events on the reactor safety and well as coupling between reactor and the converter are parts of this document.

Saied M Soliman

Indian Academy of Sciences (India)

Saied M Soliman. Articles written in Journal of Chemical Sciences. Volume 127 Issue 9 September 2015 pp 1547-1556. Molecular structure investigation and tautomerism aspects of ()-3-benzylideneindolin-2-one · Assem Barakat Abdullah Mohammed Al-Majid Mohammad Shahidul Islam M Ali Saied M Soliman ...

M Majhi

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. M Majhi. Articles written in Bulletin of Materials Science. Volume 38 Issue 5 September 2015 pp 1195-1203. CoCl2 reinforced polymeric nanocomposites of conjugated polymer (polyaniline) and its conductive properties · M Majhi R B Choudhary P Maji · More Details Abstract ...

M Sujatha

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. M Sujatha. Articles written in Bulletin of Materials Science. Volume 23 Issue 1 February 2000 pp 39-45 Metallic Materials. Role of diffusional coherency strain theory in the discontinuous precipitation in Mg–Al alloy · K T Kashyap C Ramachandra M Sujatha B Chatterji.

Alterations of M1 and M4 acetylcholine receptors in the genetically dystonic (dtsz) hamster and moderate antidystonic efficacy of M1 and M4 anticholinergics.

Science.gov (United States)

Hamann, Melanie; Plank, Jagoda; Richter, Franziska; Bode, Christoph; Smiljanic, Sinisa; Creed, Meaghan; Nobrega, José N; Richter, Angelika

2017-08-15

Striatal cholinergic dysfunction has been suggested to play a critical role in the pathophysiology of dystonia. In the dt sz hamster, a phenotypic model of paroxysmal dystonia, M1 antagonists exerted moderate antidystonic efficacy after acute systemic administration. In the present study, we examined the effects of the M4 preferring antagonist tropicamid and whether long-term systemic or acute intrastriatal injections of the M1 preferring antagonist trihexyphenidyl are more effective in mutant hamsters. Furthermore, M1 and M4 receptors were analyzed by autoradiography and immunohistochemistry. Tropicamide retarded the onset of dystonic attacks, as previously observed after acute systemic administration of trihexyphenidyl. Combined systemic administration of trihexyphenidyl (30mg/kg) and tropicamide (15mg/kg) reduced the severity in acute trials and delayed the onset of dystonia during long-term treatment. In contrast, acute striatal microinjections of trihexyphenidyl, tropicamid or the positive allosteric M4 receptor modulator VU0152100 did not exert significant effects. Receptor analyses revealed changes of M1 receptors in the dorsomedial striatum, suggesting that the cholinergic system is involved in abnormal striatal plasticity in dt sz hamsters, but the pharmacological data argue against a crucial role on the phenotype in this animal model. However, antidystonic effects of tropicamide after systemic administration point to a novel therapeutic potential of M4 preferring anticholinergics for the treatment of dystonia. Copyright © 2017 IBRO. Published by Elsevier Ltd. All rights reserved.

S/M/Othering

Science.gov (United States)

McClure, Marissa

2014-01-01

Recent scholarship in art education has introduced complex discourses of mothering, m/othering curriculum, (m)others), m(other)work, family structures that confront myths of the nuclear family, non-Western motherhoods, and disability. Feminist artists and activists have long confronted cultural constructions of motherhood and the pregnant,…

FTO, m6 Am , and the hypothesis of reversible epitranscriptomic mRNA modifications.

Science.gov (United States)

Mauer, Jan; Jaffrey, Samie R

2018-05-12

The fate of mRNA is regulated by epitranscriptomic nucleotide modifications, the most abundant of which is N 6 -methyladenosine (m 6 A). Although the pattern and distribution of m 6 A in mRNA is mediated by specific methyltransferases, a recent hypothesis is that specific demethylases or 'erasers' allow m 6 A to be dynamically reversed by signaling pathways. In this Review, we discuss the data in support and against this model. New insights into the function of fat mass and obesity-associated protein (FTO), the original enzyme thought to be an m 6 A eraser, reveal that its physiologic target is not m 6 A, but instead is N 6 ,2'-O-dimethyladenosine (m 6 A m ). Another m 6 A demethylase, ALKBH5, appears to have functions limited to sperm development in normal mice. Overall, the majority of the data suggest that m 6 A is generally not reversible, although m 6 A may be susceptible to demethylation in pathophysiological states such as cancer. © 2018 Federation of European Biochemical Societies.

G M Ballabh

Indian Academy of Sciences (India)

Home; Journals; Resonance – Journal of Science Education. G M Ballabh. Articles written in Resonance – Journal of Science Education. Volume 10 Issue 8 August 2005 pp 6-24 General Article. Dynamics of the Sun-Earth-Moon System · S M Alladin G M Ballabh · More Details Fulltext PDF ...

R M Sangshetti

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. R M Sangshetti. Articles written in Bulletin of Materials Science. Volume 34 Issue 5 August 2011 pp 1027-1031. Combustion synthesis and structural characterization of Li–Ti mixed nanoferrites · R M Sangshetti V A Hiremath V M Jali · More Details Abstract Fulltext PDF.

Mida teevad mõtted, kui nad "mõlguvad"? / Ene Vainik

Index Scriptorium Estoniae

Vainik, Ene, 1964-

2013-01-01

Kognitiivsest semantikast, eriti kehapõhisuse teooriast lähtudes, uuritakse, milline kehaline kogemus on motiveerinud sõna "mõlkuma" kasutuselevõtmist perioodilisi mõtteprotsesse tähistava verbina

M Selvam

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. M Selvam. Articles written in Bulletin of Materials Science. Volume 36 Issue 4 August 2013 pp 719-727. Effect of plating time on growth of nanocrystalline Ni–P from sulphate/glycine bath by electroless deposition method · N Latha V Raj M Selvam · More Details Abstract Fulltext ...

UH-60M Black Hawk Helicopter (UH-60M Black Hawk)

Science.gov (United States)

2016-12-01

Selected Acquisition Report (SAR) RCS: DD-A&T(Q&A)823-341 UH-60M Black Hawk Helicopter (UH-60M Black Hawk ) As of FY 2017 President’s Budget Defense...Acquisition Management Information Retrieval (DAMIR) March 21, 2016 18:25:45 UNCLASSIFIED UH-60M Black Hawk December 2015 SAR March 21, 2016 18...Operational Requirements Document OSD - Office of the Secretary of Defense O&S - Operating and Support PAUC - Program Acquisition Unit Cost UH-60M Black Hawk

Theoretical analysis of nuclear reactors (Phase III), I-V, Part III, Reactor poisoning; Razrada metoda teorijske analize nuklearnih reaktora (III faza) I-IV, III Deo, Zatrovanje reaktora

Energy Technology Data Exchange (ETDEWEB)

Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1963-01-15

Report on calculation of poisoning in experimental and power reactor includes four parts. Part one describes the influence of poisoning on the physical parameters of a reactor. part two includes transformation of differential equations for iodine and xenon. It was needed for easier solution of of differential equation using the analog computer. This calculation was done for RA reactor operating at 5 MW power. The RA reactor was used an example of calculation by the proposed method. Part four shows the application of the method for calculating the Calder Hall power reactor.

Screening the Medicines for Malaria Venture "Malaria Box" against the Plasmodium falciparum aminopeptidases, M1, M17 and M18.

Directory of Open Access Journals (Sweden)

Alessandro Paiardini

Full Text Available Malaria is a parasitic disease that remains a global health burden. The ability of the parasite to rapidly develop resistance to therapeutics drives an urgent need for the delivery of new drugs. The Medicines for Malaria Venture have compounds known for their antimalarial activity, but not necessarily the molecular targets. In this study, we assess the ability of the "MMV 400" compounds to inhibit the activity of three metalloaminopeptidases from Plasmodium falciparum, PfA-M1, PfA-M17 and PfM18 AAP. We have developed a multiplex assay system to allow rapid primary screening of compounds against all three metalloaminopeptidases, followed by detailed analysis of promising compounds. Our results show that there were no PfM18AAP inhibitors, whereas two moderate inhibitors of the neutral aminopeptidases PfA-M1 and PfA-M17 were identified. Further investigation through structure-activity relationship studies and molecular docking suggest that these compounds are competitive inhibitors with novel binding mechanisms, acting through either non-classical zinc coordination or independently of zinc binding altogether. Although it is unlikely that inhibition of PfA-M1 and/or PfA-M17 is the primary mechanism responsible for the antiplasmodial activity reported for these compounds, their detailed characterization, as presented in this work, pave the way for their further optimization as a novel class of dual PfA-M1/PfA-M17 inhibitors utilising non-classical zinc binding groups.

Mass determination of moment magnitudes M w and establishing the relationship between M w and M L for moderate and small Kamchatka earthquakes

Science.gov (United States)

Abubakirov, I. R.; Gusev, A. A.; Guseva, E. M.; Pavlov, V. M.; Skorkina, A. A.

2018-01-01

The average relationship is established between the basic magnitude for the Kamchatka regional catalog, M L , and modern moment magnitude M w. The latter is firmly tied to the value of the source seismic moment M 0 which has a direct physical meaning. M L magnitude is not self-reliant but is obtained through the conversion of the traditional Fedotov's S-wave energy class, K S1,2 F68 . Installation of the digital seismographic network in Kamchatka in 2006-2010 permitted mass estimates of M 0 and M w to be obtained from the regional data. In this paper we outline a number of techniques to estimate M 0 for the Kamchatka earthquakes using the waveforms of regional stations, and then compare the obtained M w estimates with each other and with M L , based on several hundred earthquakes that took place in 2010-2014. On the average, for M w = 3.0-6.0, M w = M L -0.40; this relationship allows obtaining M w estimates (proxy- M w) for a large part of the regional earthquake catalog with M L = 3.4-6.4 ( M w = 3.0-6.0).

The challenges of M2M massive access in wireless cellular networks

Directory of Open Access Journals (Sweden)

Andrea Biral

2015-02-01

Full Text Available The next generation of communication systems, which is commonly referred to as 5G, is expected to support, besides the traditional voice and data services, new communication paradigms, such as Internet of Things (IoT and Machine-to-Machine (M2M services, which involve communication between Machine-Type Devices (MTDs in a fully automated fashion, thus, without or with minimal human intervention. Although the general requirements of 5G systems are progressively taking shape, the technological issues raised by such a vision are still partially unclear. Nonetheless, general consensus has been reached upon some specific challenges, such as the need for 5G wireless access networks to support massive access by MTDs, as a consequence of the proliferation of M2M services. In this paper, we describe the main challenges raised by the M2M vision, focusing in particular on the problems related to the support of massive MTD access in current cellular communication systems. Then we analyze the most common approaches proposed in the literature to enable the coexistence of conventional and M2M services in the current and next generation of cellular wireless systems. We finally conclude by pointing out the research challenges that require further investigation in order to provide full support to the M2M paradigm.

Different G2/M accumulation in M059J and M059K cells after exposure to DNA double-strand break-inducing agents

International Nuclear Information System (INIS)

Holgersson, Asa; Heiden, Thomas; Castro, Juan; Edgren, Margareta R.; Lewensohn, Rolf; Meijer, Annelie E.

2005-01-01

Purpose: To investigate and compare the cell cycle progression in relation to cell death in the human glioma cell lines, M059J and M059K, after exposure to DNA double-strand break-inducing agents. Methods and materials: The M059J and M059K cells, deficient and proficient in the catalytic subunit of the DNA-dependent protein kinase, respectively, were exposed to 1 and 4 Gy of photons or accelerated nitrogen ions. In addition, M059J and M059K cells were treated with 10 and 40 μg/mL of bleomycin for 30 min, respectively. Cell cycle progression, monitored by DNA flow cytometry, was measured up to 72 h after treatment. Results: M059J, but not M059K, cells displayed G 2 /M accumulation after low linear energy transfer irradiation. High linear energy transfer radiation exposure however, resulted in a substantial increase of M059K cells in the G 2 /M phase detected at 48 h. At 72 h, the number of cells in the G 2 /M phase was equivalent to its control. M059J cells accumulated mainly in S phase after high linear energy transfer irradiation. In contrast to M059K, M059J cells were still blocked at 72 h. Bleomycin induced G 2 /M accumulation for both M059J and M059K cells detected 24 h after treatment. At 48 h, the percentage of bleomycin-treated M059J cells in G 2 /M phase remained high, and the number of M059K cells had decreased to control levels. Neither cell line showed cell cycle arrest (≤10 h) after exposure to these agents. Conclusion: Distinct cell cycle block and release is dependent on the complexity of the induced DNA damage and the presence of the DNA-dependent protein kinase catalytic subunit

M Saha Sarkar

Indian Academy of Sciences (India)

Home; Journals; Pramana – Journal of Physics. M Saha Sarkar. Articles written in Pramana – Journal of Physics. Volume 57 Issue 1 July 2001 pp 165-169 Contributed Papers : Nuclear spectroscopy. Level structures ofMo – A comparative study · J M Chatterjee M Saha Sarkar S Bhattacharya P Banerjee S Sarkar R P Singh ...

Improving Student Understanding of Magmatic Differentiation Using an M&M Magma Chamber

Science.gov (United States)

Wirth, K. R.

2003-12-01

Many students, especially those in introductory geology courses, have difficulty developing a deep understanding of the processes of magmatic differentiation. In particular, students often struggle to understand Bowen's reaction series and fractional crystallization. The process of fractional crystallization by gravity settling can be illustrated using a model magma chamber consisting of M&M's. In this model, each major cation (e.g., Si, Ti, Al, Fe, Mg, Ca, Na, K) is represented by a different color M&M; other kinds of differently colored or shaped pieces could also be used. Appropriate numbers of each color M&M are combined to approximate the cation proportions of a basaltic magma. Students then fractionate the magma by moving M&M's to the bottom of the magma chamber forming a series of cumulus layers; the M&M's are removed in the stoichiometric proportions of cations in the crystallizing minerals (e.g., olivine, pyroxene, feldspars, quartz, magnetite, ilmenite). Students observe the changing cation composition (proportions of colors of M&M's) in the cumulus layers and in the magma chamber and graph the results using spreadsheet software. More advanced students (e.g., petrology course) can classify the cumulates and resulting liquid after each crystallization step, and they can compare the model system with natural magmatic systems (e.g., absence of important fractionating phases, volatiles). Students who have completed this exercise generally indicate a positive experience and demonstrate increased understanding of Bowen's reaction series and fractionation processes. They also exhibit greater familiarity with mineral stoichiometry, classification, solid-solution in minerals, element behavior (e.g., incompatibility), and chemical variation diagrams. Other models (e.g., paths of equilibrium and fractional crystallization on phase diagrams) can also be used to illustrate differentiation processes in upper level courses (e.g., mineralogy and petrology).

108mAg and 110mAg in crassostrea gigas

International Nuclear Information System (INIS)

Ishikawa, Y.; Sato, N.; Nakamura, E.; Sekine, T.; Yoshihara, K.

1992-01-01

Accumulation of radiosilver 108m Ag and 110m Ag in oysters (Crassostrea gigas) and their behavior in marine environments has been studied in the northeast Pacific coast in Japan. Enrichment of radiosilver in oysters depends on topographical conditions; significant bioaccumulation occurred in open bays, while it was hardly observed in bays with narrow shaped entrances. From these observations difference of the behavior of radiosilver between open and nearly closed bays is suggested. 110m Ag in oysters decayed with an effective half-life of about 150 days for both the Chinese nuclear weapon test and the Chernobyl accident. In contrast to radiosilver, the fission product nuclide 137 Cs was almost independent of topographical conditions, and its concentration was constant. 110m Ag bioaccumulation in oysters after the Chernobyl accident in 1986 was found in both open and nearly closed bays, the lattershowing much lower concentration of radiosilver than the former. Specific activity of 108m Ag in oysters was determined in bays open to the Pacific Oceans. (author) 13 refs.; 4 figs.; 3 tabs

Inteligencias múltiples

OpenAIRE

Howard Gardner

2005-01-01

El presente Trabajo Fin de Grado de Educación Infantil está centrado en la Teoría de las Inteligencias Múltiples, la cual, pretende ampliar el alcance del potencial humano más allá de los confines de la cifra del cociente intelectual. Por ello, primeramente se describirán las características más notorias de cada una de las inteligencias múltiples para así, posteriormente, poder acercarnos a una visión más práctica de las mismas en el aula. Con este proyecto se pretende profundizar en las ...

Photo catalytic degradation of m-cresol; Degradacion fotocatalitica de m-cresol

Energy Technology Data Exchange (ETDEWEB)

Chavarria C, N.; Jimenez B, J.; Garcia S, I.; Valenzuela, M.A. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

2002-07-01

The degradation of m-cresol was studied, a persistent organic compound that is consider a pollutant of residual water. There for a photo catalysis system was used, which consists in a glass reactor where is placed an aqueous solution of m-cresol and a semiconductor is added, in this case, titanium oxide. The solutions were irradiated with ultraviolet light and the surplus m-cresol was measured by UV vis spectrometry. The results indicate that the m-cresol is degraded until a 40% after 5 hours of irradiation in such conditions. (Author)

Description of Radiation Sources Installed at the French Atomic Energy Commissariat; Description de sources de rayonnement installees au commissariat a l'energie atomique; Opisanie istochnikov oblucheniya, nakhodyashchikhsya v frantsuzskom komissariate po atomnoj ehnergii; Descripcion de las fuentes de radiaciones instaladas en el commissariat a l'energie

Energy Technology Data Exchange (ETDEWEB)

Leveque, P

1960-07-15

organicas, ya que el flujo epitermico y rapido provoca la activacion de la mayor parte de los productos sometidos a la irradiacion. A continuacion, el autor describe las instalaciones del Centro de Aplicaciones Atomicas de Lyon creado en las proximidades de dicha ciudad por un grupo de industriales. Este Centro, que segun esta previsto comenzara a funcionar en 1960, tendra un caracter semi-industrial (para comenzar, una fuente de cobalto-60 de 3 000 curies y mas adelante, otra de 40 000 curies) y permitira realizar operaciones de irradiacion de una manera continua. (author) [Russian] Prezhde vsego avtor daet opisanie chetyrekh ustanovok, nakhodyashchikhsya v yadernom issledovatel'skom tsentre v Sakleh. - Laboratornyj istochnik v 600 kyuri kobal'ta-60; ispol'zuemyj pribor yavlyaetsya prostym i bezopasnym, no ne daet vozmozhnosti izmenyat' potok gamma-luchej. - Pribor, sostoyashchij iz semi istochnikov kobal'ta-60 (samyj moshchnyj v 1000 kyuri), ustanovlennykh v betonnoj kamere; pnevmaticheski j pribor pozvolyaet ustanovit' odin ili neskol'ko neobkhodimykh istochnikov v rabochem polozhenii. - Kamera vmeshchaet 100 sterzhnej yadernogo goryuchego ot novogo reaktora EL3; chast' ehtoj kamery prisposoblena dlya okhlazhdeniya, chto pozvolit proizvodit' opyty nad konservatsiej pishchevykh produktov dejstviem oblucheniya. - Vertikal'nye kanaly reaktora EL 2, tak nazyvaemye ''okna khimika''; kogda ehti kanaly obernuty kadmievoj fol'goj, dostigaemyj potok gamma-luchej perekhodit so 100000 na 200000 rentgeno/chasov, no oni mogut sluzhit' tol'ko dlya oblucheniya organicheskikh materialov, tak kak imeetsya aktivatsiya bol'shej chasti obluchaemykh produktov pri pomoshchi bystrogo ehpitermicheskogo potoka. Zatem avtor daet opisanie pribora, ustanovlennogo v Lionskom tsentre po ispol'zovaniyu atomov, postroennogo okolo Liona gruppoj promyshlennikov. EHtot pribor, pusk v ehkspluatatsiyu kotorogo predusmotren na nachalo 1960 goda, budet nosit' polupromyshlennyj kharakter (istochnik kobal'ta-60

β-adrenergic-stimulated macrophages: Comprehensive localization in the M1–M2 spectrum

Science.gov (United States)

Lamkin, Donald M.; Ho, Hsin-Yun; Ong, Tiffany H.; Kawanishi, Carly K.; Stoffers, Victoria L.; Ahlawat, Nivedita; Ma, Jeffrey C.Y.; Arevalo, Jesusa M. G.; Cole, Steve W.; Sloan, Erica K.

2016-01-01

β-adrenergic signaling can regulate macrophage involvement in several diseases and often produces anti-inflammatory properties in macrophages, which are similar to M2 properties in a dichotomous M1 vs. M2 macrophage taxonomy. However, it is not clear that β-adrenergic-stimulated macrophages may be classified strictly as M2. In this in vitro study, we utilized recently published criteria and transcriptome-wide bioinformatics methods to map the relative polarity of murine β-adrenergic-stimulated macrophages within a wider M1–M2 spectrum. Results show that β-adrenergic-stimulated macrophages did not fit entirely into any one predefined category of the M1–M2 spectrum but did express genes that are representative of some M2 side categories. Moreover, transcript origin analysis of genome-wide transcriptional profiles located β-adrenergic-stimulated macrophages firmly on the M2 side of the M1–M2 spectrum and found active suppression of M1 side gene transcripts. The signal transduction pathways involved were mapped through blocking experiments and bioinformatics analysis of transcription factor binding motifs. M2-promoting effects were mediated specifically through β2-adrenergic receptors and were associated with CREB, C/EBPβ, and ATF transcription factor pathways but not with established M1–M2 STAT pathways. Thus, β-adrenergic-signaling induces a macrophage transcriptome that locates on the M2 side of the M1–M2 spectrum but likely accomplishes this effect through a signaling pathway that is atypical for M2-spectrum macrophages. PMID:27485040

Modeling and simulation of M/M/c queuing pharmacy system with adjustable parameters

Science.gov (United States)

Rashida, A. R.; Fadzli, Mohammad; Ibrahim, Safwati; Goh, Siti Rohana

2016-02-01

This paper studies a discrete event simulation (DES) as a computer based modelling that imitates a real system of pharmacy unit. M/M/c queuing theo is used to model and analyse the characteristic of queuing system at the pharmacy unit of Hospital Tuanku Fauziah, Kangar in Perlis, Malaysia. The input of this model is based on statistical data collected for 20 working days in June 2014. Currently, patient waiting time of pharmacy unit is more than 15 minutes. The actual operation of the pharmacy unit is a mixed queuing server with M/M/2 queuing model where the pharmacist is referred as the server parameters. DES approach and ProModel simulation software is used to simulate the queuing model and to propose the improvement for queuing system at this pharmacy system. Waiting time for each server is analysed and found out that Counter 3 and 4 has the highest waiting time which is 16.98 and 16.73 minutes. Three scenarios; M/M/3, M/M/4 and M/M/5 are simulated and waiting time for actual queuing model and experimental queuing model are compared. The simulation results show that by adding the server (pharmacist), it will reduce patient waiting time to a reasonable improvement. Almost 50% average patient waiting time is reduced when one pharmacist is added to the counter. However, it is not necessary to fully utilize all counters because eventhough M/M/4 and M/M/5 produced more reduction in patient waiting time, but it is ineffective since Counter 5 is rarely used.

Nondestructive, fast methods for burn-up study

International Nuclear Information System (INIS)

Schaechter, L.; Hacman, D.; Mot, O.

1977-01-01

Nondestructive methods, based on high resolution-spectrometry successfully applied at Institute for Atomic Physics are presented. These methods are preferred to destructive chemical methods; the latter being costly and lengthy and not suitable for statistical prediction of nuclear fuel behaviour. The following methods are developed: methods for determining the burn up of fuel elements and fuel assemblies; a method for determining the U 235 and Pu 239 contributions to the burn up and a code written in FORTRAN IV for numerical calculation of Pu 239 fission vs. burn up; a high precision method for burnup determination by adding burnable poison; a method for prediction of specific power distribution in the fuel elements of a research or power reactors; a method for determining the power output of the fuel element in an operating power reactor; a method for determining the content of Pu 239 of the fuel element irradiated in a reactor. The results which were obtained by these methods improved the fuel management at the VVR-S reactor at Institute for Atomic Physics, Bucharest and may be applied to other reactor types [fr

Chemoprevention by WR-2721

Energy Technology Data Exchange (ETDEWEB)

Grdina, D.J. [Argonne National Lab., IL (United States)]|[Chicago Univ., IL (United States). Dept. of Radiation and Cellular Oncology; Carnes, B.A. [Argonne National Lab., IL (United States)

1993-05-01

WR-2721 [S-2-(3-aminopropylamino)ethylphosphorothioic acid] is an effective chemopreventive agent. C57BL {times} BALB/c F{sub 1} female mice, were exposed to a single whole-body dose of 206 cGy from a {sup 60}Co photon source. Those groups treated with VATR-2721 (400 mg/kg) were administered the agent i.p. 30 min prior to irradiation. Over 90% of deaths were determined to be due to tumor involvement. WR-2721 afforded significant protection against life shortening due to radiation-induced tumors of connective tissue and epithelial tissue origins. Subsequent survival time in WR-2721-treated and irradiated animals as compared to matched irradiated-only controls was extended up to 59 days. A single exposure of animals to VVR-2721 did not affect the cumulative survival curves for unirradiated mice. WR-2721 possesses chemopreventive properties which can be clinically exploited to reduce the risk to therapy-induced secondary cancers in patients who otherwise would have an excellent prognosis for cure and long-term survival.

Chemoprevention by WR-2721

Energy Technology Data Exchange (ETDEWEB)

Grdina, D.J. (Argonne National Lab., IL (United States) Chicago Univ., IL (United States). Dept. of Radiation and Cellular Oncology); Carnes, B.A. (Argonne National Lab., IL (United States))

1993-01-01

WR-2721 [S-2-(3-aminopropylamino)ethylphosphorothioic acid] is an effective chemopreventive agent. C57BL [times] BALB/c F[sub 1] female mice, were exposed to a single whole-body dose of 206 cGy from a [sup 60]Co photon source. Those groups treated with VATR-2721 (400 mg/kg) were administered the agent i.p. 30 min prior to irradiation. Over 90% of deaths were determined to be due to tumor involvement. WR-2721 afforded significant protection against life shortening due to radiation-induced tumors of connective tissue and epithelial tissue origins. Subsequent survival time in WR-2721-treated and irradiated animals as compared to matched irradiated-only controls was extended up to 59 days. A single exposure of animals to VVR-2721 did not affect the cumulative survival curves for unirradiated mice. WR-2721 possesses chemopreventive properties which can be clinically exploited to reduce the risk to therapy-induced secondary cancers in patients who otherwise would have an excellent prognosis for cure and long-term survival.

Neutron activation analysis in Romania

International Nuclear Information System (INIS)

Apostolescu, St.

1985-01-01

The following basic nuclear facilities are used for neutron activation analysis: a 2000 KW VVR-S Nuclear Reactor, a U-200 Cyclotron, a 30 MeV Betatron, several 14 MeV neutron generators and a king size High Voltage tandem Van de'Graaff accelerator. The main domains of application of the thermal neutron activation analysis are: geology and mining, processing of materials, environment and biology, achaeology. Epithermal neutron activation analysis has been used for determination of uranium and thorium in ores with high Th/U ratios or high rare earth contents. One low energy accelerator, used as 14.1 Mev neutron source, is provided with special equipmen for oxigen and low mass elements determination. An useful alternating way to support fast neutron activation analysis is an accurate theoretical description of the fast neutron induced reactions based on the statistical model (Hauser-Feubach STAPRE code) and the preequilibrium decay geometry dependent model. A gravitational sample changer has been installed at the end of a beam line of the Cyclotron, which enables to perform charged particles activation analysis for protein determination in grains

Renee M Borges

Indian Academy of Sciences (India)

Renee M Borges · More Details Fulltext PDF. Volume 7 Issue 11 November 2002 pp 2-5 Article-in-a-Box. Stephen Jay Gould: A View of Life · Renee M Borges · More Details Fulltext PDF. Volume 10 Issue 7 July 2005 pp 21-33 General Article. Polemics and Synthesis: Ernst Mayr and Evolutionary Biology · Renee M Borges.

El Che - más que médico

OpenAIRE

Natalia I. Osorio Curbelo

2015-01-01

Revolucionario, dirigente político, comandante guerrillero, intelectual y médico.  Uno de los íconos del siglo XX.  Nació en Rosario, Argentina, el 14 de junio de 1928. En 1938, con apenas 10 años, el padre le enseñó a jugar Ajedrez en el transcurso del año, deporte que no dejaría de practicar nunca más y lo estudiaría por siempre. En 1939 supo de la existencia de Cuba, pues teniendo 11 años, cuando vivía en Alta Gracia, en Buenos Aires se desarrollaba la VII Olimpiada de Ajedrez y el más con...

Seamless communication in supply chains based on M2M technology

Directory of Open Access Journals (Sweden)

Walid Moneimne

2016-12-01

Full Text Available Background: Access to information is the key element in the successful and efficient organization of transport & logistic processes. The importance of real-time access to information is confirmed by a panel workshop carried out with support of design thinking methodology. There are two ways of gaining access to the right information - manual, where human agency is needed and fully automatic, where new M2M technology is implemented. Implementation of such technology improves seamless communication during transport execution and allows real-time access to needed information. The aim of the paper is to evaluate the influence of the effectiveness of using M2M technology and traditional way of communication as well as data gathering in order to ensure seamless communication in the supply chain. Methods: Survey, design thinking, desk research and real case study results were used in the paper. Results and conclusions: Seamless communication and implementation of M2M technology within the whole supply (including modes of transport and transport units chain is a backbone of the lean and reliable digital supply chain.

M S Castro

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. M S Castro. Articles written in Bulletin of Materials Science. Volume 34 Issue 6 October 2011 pp 1213-1217. Electrical and microstructural properties of CaTiO3-doped K1/2Na1/2NbO3-lead free ceramics · L Ramajo R Parra M A Ramírez M S Castro · More Details Abstract ...

Annex 3 - Testing the microstructure of the fuel element with metal uranium with aluminium cladding; Prilog 3 - Ispitivanje mikrostrukture gorivnog elementa na bazi metalnog urana sa aluminijumskom kosuljicom

Energy Technology Data Exchange (ETDEWEB)

Milosevic, S; Momcilovic, I [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1961-12-15

Based on the uranium microstructure in the fuel element, i.e. grain size, presence of other phases, porosity and the position of metal connections, some data could be obtained about the mechanical and thermal treatment of the uranium during fuel element fabrication. The mentioned characteristics could indicate the behaviour of the fuel under reactor operating conditions taking into account its stable dimensions and roughness of its surfaces. Na osnovu mikrostrukture urana u gorivnom elementu, odnosno velicine i oblika njegovih kristalnih zrna, prisustva drugih faza, pozoziteta kao i rasporeda metalnih ukljucaka, mogu se dobiti izvesni podaci o tome koje je postupke mehanickog i termickog tretiranja pretrpeo uran u pripremi za gorivni elemenat. Prethodne karakteristike takodje mogu da daju predstavu o tome kako ce se gorivo ponasati u uslovima rada reaktora, s obzirom na njegovu dimenzionu stabilnost i ogrubljivanje njegove povrsine (author)

Half-lives of isomeric levels of 107mAg, 109mAg and 103mRh photoactivated by 60Co γ-ray irradiation

International Nuclear Information System (INIS)

Yoshida, Eiji; Kobayashi, Takashige; Kojima, Yasuaki; Shizuma, Kiyoshi

2000-01-01

Photoactivation by γ-rays from 60 Co of 10 kCi has been performed for isomers of 107m Ag, 109m Ag and 103m Rh and half-lives of these isomers were determined. Gamma-rays emitted from 107m Ag and 109m Ag were measured with a low-background Ge detector and internal conversion electrons from 103m Rh were measured with a 2π gas flow counter. The half-lives obtained are: 107m Ag: 44.5±0.8 s, 109m Ag: 38.0±1.2 s and 103m Rh: 54.8±3.8 min. The results are in agreement with previous values obtained by different excitation methods

ZMS regulation of M2 muscarinic receptor mRNA stability requires protein factor

International Nuclear Information System (INIS)

Zhang Yongfang; Xia Zongqin; Hu Ya'er

2010-01-01

Aim The aim of this work is to study the elevation mechanism of ZMS on muscarinic M2 receptor mRNA expression. Methods Actinomycin D was added to cultured CHOm2 cells to stop the de novo synthesis of M2 receptor mRNA and samples were taken at various times to determine the time course of mRNA of M2 receptor with real-time quantitative RT-PCR. Half-life of M2 receptor mRNA and the effect of ZMS on the half-life was obtained from the slope of the exponential curves. Cycloheximide was added at 4 h prior to and 24 h after the addition of ZMS to examine the effect of de novo protein synthesis on the action of ZMS. Results The half-life of m2 mRNA was prolonged by ZMS treatment without cycloheximide (4.75±0.54 h and 2.13 h±0.23 h for ZMS and vehicle treated groups, respectively, P<0.05). When cycloheximide was added to the culture medium 4h prior to the addition of ZMS, the effect of ZMS in prolonging the half-life of m2 mRNA disappeared (3.06 h±0.23 h and 3.00 h±l.20 h for cells with and without ZMS, respectively). However, when the ZMS was added to the medium 24h prior to the addition of cycloheximide, the action of ZMS was not abolished by cycloheximide (half-life was 5.43 h±1.13 h and 2.46 h±0.09 h for cells with and without ZMS, respectively). Conclusion These data suggest that de novo protein synthesis was required for the increase in M2 mRNA stability induced by ZMS. (authors)

ENT mängis mõisajanti ja laulis vene romansse / Margit Bunder

Index Scriptorium Estoniae

Bunder, Margit, 1970-

2004-01-01

Eesti Näitejuhtide Teatritrupp mängis Mooste mõisas ja mõisa pargis muusikalist jantmängu "Oh ajad, oh kombed" ja esitas Pushkini ja Lermontovi luulet vaheldumisis vene romanssidega. Ka näitejuhtide suvekoolist

Understanding the Relationships between mHealth Apps' Characteristics, Trialability, and mHealth Literacy.

Science.gov (United States)

Lin, Trisha T C; Bautista, John Robert

2017-04-01

The widespread adoption of mobile phones has increased the potential of mHealth to improve health communication and health outcomes because these devices could serve as a ubiquitous and affordable means to disseminate health information to large populations. Given that mHealth apps offer free or limited trials as part of promotional strategies, potential users' trialability is a critical step of the preadoption process. Drawing from Rogers' diffusion of innovation theory, this study examines the relationships of adopters' perceived characteristics of mHealth apps (i.e., relative advantage, complexity, compatibility, and observability) with their trialability. It further investigates how the perceived control of mobile devices and trialability of mHealth apps influence two dimensions of mHealth literacy, namely seeking and appraisal of health information. This web survey recruited 295 young mHealth app users from a Singaporean university. Results of partial least squares regression show that the observability of mHealth apps is the only factor positively related to mHealth trialability. Perceived control of mobile devices and trialability of mHealth apps are positively associated with seeking and appraisal of health information. Practical and theoretical implications to mHealth are discussed.

La-related protein 1 (LARP1) represses terminal oligopyrimidine (TOP) mRNA translation downstream of mTOR complex 1 (mTORC1)

DEFF Research Database (Denmark)

Fonseca, Bruno; Zakaria, Chadi; Jia, J J

2015-01-01

is incompletely understood. Here, we report that LARP1 functions as a key repressor of TOP mRNA translation downstream of mTORC1. Our data show the following: (i) LARP1 associates with mTORC1 via RAPTOR; (ii) LARP1 interacts with TOP mRNAs in an mTORC1-dependent manner; (iii) LARP1 binds the 5′TOP motif...

President külastas Palmse mõisat ja mööblitootjat

Index Scriptorium Estoniae

2009-01-01

President Toomas Hendrik Ilves külastas 19. oktoobril 2009 Haljalas pehme mööbli tootmisega tegelevat Bellus Furniture OÜd. Riigipea külastas ka Palmse mõisa, kus tutvus koolituskeskusega ja mõisa arendamise kavadega

Empirical Global Relations Converting M S and m b to Moment Magnitude

Science.gov (United States)

Scordilis, E. M.

2006-04-01

The existence of several magnitude scales used by seismological centers all over the world and the compilation of earthquake catalogs by many authors have rendered globally valid relations connecting magnitude scales a necessity. This would allow the creation of a homogeneous global earthquake catalog, a useful tool for earthquake research. Of special interest is the definition of global relations converting different magnitude scales to the most reliable and useful scale of magnitude, the moment magnitude, M W. In order to accomplish this, a very large sample of data from international seismological sources (ISC, NEIC, HRVD, etc.) has been collected and processed. The magnitude scales tested against M W are the surface wave magnitude, M S, the body wave magnitude, m b, and the local magnitude, M L. The moment magnitudes adopted have been taken from the CMT solutions of HRVD and USGS. The data set used in this study contains 20,407 earthquakes, which occurred all over the world during the time period 1.1.1976-31.5.2003, for which moment magnitudes are available. It is shown that well-defined relations hold between M W and m b and M S and that these relations can be reliably used for compiling homogeneous, with respect to magnitude, earthquake catalogs.

r m o gemson

Indian Academy of Sciences (India)

Home; Journals; Sadhana. R M O GEMSON. Articles written in Sadhana. Volume 41 Issue 12 December 2016 pp 1473-1490. A heuristic reference recursive recipe for adaptively tuning the Kalman filter statistics part-1: formulation and simulation studies · M R ANANTHASAYANAM M SHYAM MOHAN NAREN NAIK R M O ...

The Chemical Composition Contrast between M3 and M13 Revisited: New Abundances for 28 Giant Stars in M3

Science.gov (United States)

Sneden, Christopher; Kraft, Robert P.; Guhathakurta, Puragra; Peterson, Ruth C.; Fulbright, Jon P.

2004-04-01

We report new chemical abundances of 23 bright red giant members of the globular cluster M3, based on high-resolution (R~45,000) spectra obtained with the Keck I telescope. The observations, which involve the use of multislits in the HIRES Keck I spectrograph, are described in detail. Combining these data with a previously reported small sample of M3 giants obtained with the Lick 3 m telescope, we compare metallicities and [X/Fe] ratios for 28 M3 giants with a 35-star sample in the similar-metallicity cluster M13, and with Galactic halo field stars having [Fe/H]=A(Si), we derive little difference in [X/Fe] ratios in the M3, M13, or halo field samples. All three groups exhibit C depletion with advancing evolutionary state beginning at the level of the red giant branch ``bump,'' but the overall depletion of about 0.7-0.9 dex seen in the clusters is larger than that associated with the field stars. The behaviors of O, Na, Mg, and Al are distinctively different among the three stellar samples. Field halo giants and subdwarfs have a positive correlation of Na with Mg, as predicted from explosive or hydrostatic carbon burning in Type II supernova sites. Both M3 and M13 show evidence of high-temperature proton-capture synthesis from the ON, NeNa, and MgAl cycles, while there is no evidence for such synthesis among halo field stars. But the degree of such extreme proton-capture synthesis in M3 is smaller than it is in M13: the M3 giants exhibit only modest deficiencies of O and corresponding enhancements of Na, less extreme overabundances of Al, fewer stars with low Mg and correspondingly high Na, and no indication that O depletions are a function of advancing evolutionary state, as has been claimed for M13. We have also considered NGC 6752, for which Mg isotopic abundances have been reported by Yong et al. Giants in NGC 6752 and M13 satisfy the same anticorrelation of O abundances with the ratio (25Mg+26Mg)/24Mg, which measures the relative contribution of rare to

The Clothes Make the mRNA: Past and Present Trends in mRNP Fashion.

Science.gov (United States)

Singh, Guramrit; Pratt, Gabriel; Yeo, Gene W; Moore, Melissa J

2015-01-01

Throughout their lifetimes, messenger RNAs (mRNAs) associate with proteins to form ribonucleoproteins (mRNPs). Since the discovery of the first mRNP component more than 40 years ago, what is known as the mRNA interactome now comprises >1,000 proteins. These proteins bind mRNAs in myriad ways with varying affinities and stoichiometries, with many assembling onto nascent RNAs in a highly ordered process during transcription and precursor mRNA (pre-mRNA) processing. The nonrandom distribution of major mRNP proteins observed in transcriptome-wide studies leads us to propose that mRNPs are organized into three major domains loosely corresponding to 5' untranslated regions (UTRs), open reading frames, and 3' UTRs. Moving from the nucleus to the cytoplasm, mRNPs undergo extensive remodeling as they are first acted upon by the nuclear pore complex and then by the ribosome. When not being actively translated, cytoplasmic mRNPs can assemble into large multi-mRNP assemblies or be permanently disassembled and degraded. In this review, we aim to give the reader a thorough understanding of past and current eukaryotic mRNP research.

Velocity dispersions in galaxies. V. The nuclei of M31 and M32

International Nuclear Information System (INIS)

Morton, D.C.; Elmergreen, B.G.

1976-01-01

Stigmatic spectra between 4160 and 4385 A with 0.7 A resolution have been obtained of the central regions of M31 and M32, including their starlike nuclei, and the KO III star 51 Ori using an SEC TV sensor and the coude spectrograph of the Hale telescope. Line-of-sight velocity dispersions of sigma=130 +- 20 and 55(+10, -15) km s -1 have been determined for the nuclei of M31 and M32, respectively, by direct comparision with the star spectrum broadened by various Gaussian widths. This KO III star is a poor match in the nucleus of M31, but represents rather well the spectrum of the nucleus of M32 and the bulge of M31 at 10'' from the center

Machine-to-Machine networks: integration of M2M networks into companies' administrative networks

OpenAIRE

Pointereau, Romain

2013-01-01

This analysis will address the technical, economic and regulatory aspects and will identify the position taken by the various market actors. Integration of M2M Networks into Companies' Administrative Networks. Integración de redes M2M en redes administrativas de las empresas. Integració de xarxes M2M en xarxes administratives de les empreses.

Giant graviton interactions and M2-branes ending on multiple M5-branes

Science.gov (United States)

Hirano, Shinji; Sato, Yuki

2018-05-01

We study splitting and joining interactions of giant gravitons with angular momenta N 1/2 ≪ J ≪ N in the type IIB string theory on AdS 5 × S 5 by describing them as instantons in the tiny graviton matrix model introduced by Sheikh-Jabbari. At large J the instanton equation can be mapped to the four-dimensional Laplace equation and the Coulomb potential for m point charges in an n-sheeted Riemann space corresponds to the m-to- n interaction process of giant gravitons. These instantons provide the holographic dual of correlators of all semi-heavy operators and the instanton amplitudes exactly agree with the pp-wave limit of Schur polynomial correlators in N = 4 SYM computed by Corley, Jevicki and Ramgoolam. By making a slight change of variables the same instanton equation is mathematically transformed into the Basu-Harvey equation which describes the system of M2-branes ending on M5-branes. As it turns out, the solutions to the sourceless Laplace equation on an n-sheeted Riemann space correspond to n M5-branes connected by M2-branes and we find general solutions representing M2-branes ending on multiple M5-branes. Among other solutions, the n = 3 case describes an M2-branes junction ending on three M5-branes. The effective theory on the moduli space of our solutions might shed light on the low energy effective theory of multiple M5-branes.

Programming in Fortran M

Energy Technology Data Exchange (ETDEWEB)

Foster, I.; Olson, R.; Tuecke, S.

1993-08-01

Fortran M is a small set of extensions to Fortran that supports a modular approach to the construction of sequential and parallel programs. Fortran M programs use channels to plug together processes which may be written in Fortran M or Fortran 77. Processes communicate by sending and receiving messages on channels. Channels and processes can be created dynamically, but programs remain deterministic unless specialized nondeterministic constructs are used. Fortran M programs can execute on a range of sequential, parallel, and networked computers. This report incorporates both a tutorial introduction to Fortran M and a users guide for the Fortran M compiler developed at Argonne National Laboratory. The Fortran M compiler, supporting software, and documentation are made available free of charge by Argonne National Laboratory, but are protected by a copyright which places certain restrictions on how they may be redistributed. See the software for details. The latest version of both the compiler and this manual can be obtained by anonymous ftp from Argonne National Laboratory in the directory pub/fortran-m at info.mcs.anl.gov.

Corners in M-theory

Science.gov (United States)

Sati, Hisham

2011-06-01

M-theory can be defined on closed manifolds as well as on manifolds with boundary. As an extension, we show that manifolds with corners appear naturally in M-theory. We illustrate this with four situations: the lift to bounding 12 dimensions of M-theory on anti-de Sitter spaces, ten-dimensional heterotic string theory in relation to 12 dimensions, and the two M-branes within M-theory in the presence of a boundary. The M2-brane is taken with (or as) a boundary and the worldvolume of the M5-brane is viewed as a tubular neighborhood. We then concentrate on the (variant) of the heterotic theory as a corner and explore analytical and geometric consequences. In particular, we formulate and study the phase of the partition function in this setting and identify the corrections due to the corner(s). The analysis involves considering M-theory on disconnected manifolds and makes use of the extension of the Atiyah-Patodi-Singer index theorem to manifolds with corners and the b-calculus of Melrose.

Corners in M-theory

International Nuclear Information System (INIS)

Sati, Hisham

2011-01-01

M-theory can be defined on closed manifolds as well as on manifolds with boundary. As an extension, we show that manifolds with corners appear naturally in M-theory. We illustrate this with four situations: the lift to bounding 12 dimensions of M-theory on anti-de Sitter spaces, ten-dimensional heterotic string theory in relation to 12 dimensions, and the two M-branes within M-theory in the presence of a boundary. The M2-brane is taken with (or as) a boundary and the worldvolume of the M5-brane is viewed as a tubular neighborhood. We then concentrate on the (variant) of the heterotic theory as a corner and explore analytical and geometric consequences. In particular, we formulate and study the phase of the partition function in this setting and identify the corrections due to the corner(s). The analysis involves considering M-theory on disconnected manifolds and makes use of the extension of the Atiyah-Patodi-Singer index theorem to manifolds with corners and the b-calculus of Melrose.

C M K Nair

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. C M K Nair. Articles written in Bulletin of Materials Science. Volume 24 Issue 2 April 2001 pp 249-252 Crystal Growth. Thermal behaviour of strontium tartrate single crystals grown in gel · M H Rahimkutty K Rajendra Babu K Sreedharan Pillai M R Sudarsana Kumar C M K Nair.

Demokratiske møbler

DEFF Research Database (Denmark)

Hansen, Per H.

2014-01-01

Moderne dansk møbeldesign var totalt dominerende i efterkrigstidens forestillinger om skandinavisk design - alligevel var det IKEA, der blev verdens største møbel- og livsstilsforretning.......Moderne dansk møbeldesign var totalt dominerende i efterkrigstidens forestillinger om skandinavisk design - alligevel var det IKEA, der blev verdens største møbel- og livsstilsforretning....

Access Control in IoT/M2M - Cloud Platform

DEFF Research Database (Denmark)

Anggorojati, Bayu

Billions of devices are connected to the Internet nowadays, and the number will continue to grow in the future thanks to the advances in the electronics and telecommunication technology developments. Its application in broad aspects of human’s life brings a lot of benefits by improving productivity...... and quality of life. This paradigm, which is often called Internet of Things (IoT) or Machine-to-Machine (M2M), will provide an unprecedented opportunity to create applications and services that go far beyond the mere purpose of each participant. Many studies on the both technical and social aspects of Io......T have shown that the concern about the security and privacy play a huge role for the mass adoption of the IoT/M2M as cloud services. Among the important topics within the security and privacy, the access control is an important mechanism, which essentially manages how the important assets or resource...

Evaluation of the absorbed dose to the kidneys due to Tc99m (DTPA) / Tc99m (Mag3) and Tc99m (Dmsa)

International Nuclear Information System (INIS)

Vasquez A, M.; Murillo C, F.; Castillo D, C.; Rocha J, J.; Sifuentes D, Y.; Sanchez S, P.; Idrogo C, J.; Marquez P, F.

2015-10-01

The absorbed dose in the kidneys of adult patients has been assessed using the biokinetics of radiopharmaceuticals containing Tc 99m (DTPA) / Tc 99m (Mag3) or Tc 99m (Dmsa).The absorbed dose was calculated using the formalism MIRD and the Cristy-Eckerman representation for the kidneys. The absorbed dose to the kidneys due to Tc 99m (DTPA) / Tc 99m (Mag3), are given by 0.00466 mGy.MBq -1 / 0.00339 mGy.MBq -1 . Approximately 21.2% of the absorbed dose is due to the bladder (content) and the remaining tissue, included in biokinetics of Tc 99m (DTPA) / Tc 99m (Mag3). The absorbed dose to the kidneys due to Tc 99m (Dmsa) is 0.17881 mGy.MBq -1 . Here, 1.7% of the absorbed dose is due to the bladder, spleen, liver and the remaining tissue, included in biokinetics of Tc 99m (Dmsa). (Author)

Research nuclear reactor RA - Annual Report 1994; Istrazivacki nuklearni reaktor RA - Izvestaj za 1994. godinu

Energy Technology Data Exchange (ETDEWEB)

Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1994-12-01

Activities related to revitalisation of the RA reactor stared in 1986, were continued in 1991. A number of interventions on the reactor components were finished that are supposed to enable continuous and reliable operation. The last, and at the same time largest action, related to exchange of complete reactor instrumentation is underway, but it is behind the schedule in 1991 because the delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 56% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. In 1991 most of the existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Activities related to improvement of Russian project were continued in 1994. Control and maintenance of the reactor components was done regularly and efficiently. Extensive repair of the secondary coolant loop is almost finished and will be completed in the first part of 1995 according to existing legal procedures and IAEA recommendations. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 47 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. Research reactor RA Annual report for year 1991 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U 1994. godini nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i

Nursing and mHealth

Directory of Open Access Journals (Sweden)

Catherine Samples

2014-12-01

Full Text Available Innovations in mobile health (mHealth technology offer applications to promote wellness management and health behavior change outside of formal clinical settings. Nurses can help to move mHealth into mainstream health care by understanding its potential to change the landscape of health intervention delivery, incorporating mHealth into patients' day to day preventive care strategies, and supporting the science of mHealth's effectiveness.

RA Research reactor, Part I: Technical and operational properties of the RA reactor; Analiza sigurnosti rada Reaktora RA I-III, Deo I: Tehnicke i pogonske karakteristike reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Raisic, N; Zecevic, V; Nikolic, M; Popovic, B; Milosevic, M; Milic, M; Strugar, P; Pesic, M; Nikolic, V; Rajic, M; Radivojevic, J; Jankovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1963-02-15

RA reactor is a research reactor with rather high power density. Apart from research it is used for isotope production and industrial applications due to high reactivity excess (about 11%). It is a thermal reactor, heavy water moderated, cooled by D{sub 2}O, and H{sub 2}O, with a graphite reflector. Nominal power is 6.5 MW. Fuel is 2% enriched metal uranium, reactor core height is 1220 mm, and diameter is 1405 mm. Reactor lattice is square with lattice pitch 130 mm. There is 6 horizontal experimental channels and a graphite column. There is a total of 84 fuel channels and 45 experimental channels in the core. Maximum thermal neutron flux is 5.5 10{sup 13} n/cm{sup 2} s at nominal power level.

Ab initio study of M2AlN (M = Ti,V,Cr)

International Nuclear Information System (INIS)

Sun, Zhimei; Music, Denis; Ahuja, Rajeev; Schneider, Jochen M

2005-01-01

We have studied M 2 AlN phases, where M = Ti, V, and Cr, by means of ab initio total energy calculations. The bulk modulus of M 2 AlN increases as Ti is replaced with V and Cr by 19.0% and 26.5%, respectively, which can be understood on the basis of the increased number of valence electrons filling the p-d hybridized bonding states. The bulk modulus of M 2 AlN is generally higher than that of the corresponding M 2 AlC phase, which may be explained by an extra electron in the former phases contributing to stronger chemical bonding. This work is important for fundamental understanding of elastic properties of these ternary nitrides and may inspire future experimental research. (letter to the editor)

Autoimmunity related to IgM monoclonal gammopathy of undetermined significance. Peripheral neuropathy and connective tissue sensibilization caused by IgM M-proteins

DEFF Research Database (Denmark)

Jønsson, V; Schrøder, H D; Nolsøe, C

1988-01-01

of them, including two siblings with a demyelinating peripheral neuropathy, the IgM was bound to the myelin-associated glycoprotein (MAG) of peripheral nerves. One had axonal neuropathy with IgM activity against the peri- and endoneurium, while another case with post-infectious neuritis had IgM activity......In eight of 10 consecutive cases of IgM monoclonal gammopathy of undetermined significance (MGUS), the M-protein had specificity towards various tissues as estimated by direct and indirect immunofluorescence studies of skin and/or sural nerve biopsies. Five of the cases had neuropathy. In three...

Interactions between the HIV-1 Unspliced mRNA and Host mRNA Decay Machineries

Directory of Open Access Journals (Sweden)

Daniela Toro-Ascuy

2016-11-01

Full Text Available The human immunodeficiency virus type-1 (HIV-1 unspliced transcript is used both as mRNA for the synthesis of structural proteins and as the packaged genome. Given the presence of retained introns and instability AU-rich sequences, this viral transcript is normally retained and degraded in the nucleus of host cells unless the viral protein REV is present. As such, the stability of the HIV-1 unspliced mRNA must be particularly controlled in the nucleus and the cytoplasm in order to ensure proper levels of this viral mRNA for translation and viral particle formation. During its journey, the HIV-1 unspliced mRNA assembles into highly specific messenger ribonucleoproteins (mRNPs containing many different host proteins, amongst which are well-known regulators of cytoplasmic mRNA decay pathways such as up-frameshift suppressor 1 homolog (UPF1, Staufen double-stranded RNA binding protein 1/2 (STAU1/2, or components of miRNA-induced silencing complex (miRISC and processing bodies (PBs. More recently, the HIV-1 unspliced mRNA was shown to contain N6-methyladenosine (m6A, allowing the recruitment of YTH N6-methyladenosine RNA binding protein 2 (YTHDF2, an m6A reader host protein involved in mRNA decay. Interestingly, these host proteins involved in mRNA decay were shown to play positive roles in viral gene expression and viral particle assembly, suggesting that HIV-1 interacts with mRNA decay components to successfully accomplish viral replication. This review summarizes the state of the art in terms of the interactions between HIV-1 unspliced mRNA and components of different host mRNA decay machineries.

G M Kulkerni

Indian Academy of Sciences (India)

Home; Journals; Resonance – Journal of Science Education. G M Kulkerni. Articles written in Resonance – Journal of Science Education. Volume 3 Issue 2 February 1998 pp 77-78 Classroom. Chemical Flag · G M Kulkerni · More Details Fulltext PDF ...

Distinguishing Isomeric Peptides: The Unimolecular Reactivity and Structures of (LeuPro)M+ and (ProLeu)M+ (M = Alkali Metal).

Science.gov (United States)

Jami-Alahmadi, Yasaman; Linford, Bryan D; Fridgen, Travis D

2016-12-29

The unimolecular chemistries and structures of gas-phase (ProLeu)M + and (LeuPro)M + complexes when M = Li, Na, Rb, and Cs have been explored using a combination of SORI-CID, IRMPD spectroscopy, and computational methods. CID of both (LeuPro)M + and (ProLeu)M + showed identical fragmentation pathways and could not be differentiated. Two of the fragmentation routes of both peptides produced ions at the same nominal mass as (Pro)M + and (Leu)M + , respectively. For the litiated peptides, experiments revealed identical IRMPD spectra for each of the m/z 122 and 138 ions coming from both peptides. Comparison with computed IR spectra identified them as the (Pro)Li + and (Leu)Li + , and it is concluded that both zwitterionic and canonical forms of (Pro)Li + exist in the ion population from CID of both (ProLeu)Li + and (LeuPro)Li + . The two isomeric peptide complexes could be distinguished using IRMPD spectroscopy in both the fingerprint and the CH/NH/OH regions. The computed IR spectra for the lowest energy structures of each charge solvated complexes are consistent with the IRMPD spectra in both regions for all metal cation complexes. Through comparison between the experimental spectra, it was determined that in lithiated and sodiated ProLeu, metal cation is bound to both carbonyl oxygens and the amine nitrogen. In contrast, the larger metal cations are bound to the two carbonyls, while the amine nitrogen is hydrogen bonded to the amide hydrogen. In the lithiated and sodiated LeuPro complexes, the metal cation is bound to the amide carbonyl and the amine nitrogen while the amine nitrogen is hydrogen bonded to the carboxylic acid carbonyl. However, there is no hydrogen bond in the rubidiated and cesiated complexes; the metal cation is bound to both carbonyl oxygens and the amine nitrogen. Details of the position of the carboxylic acid C═O stretch were especially informative in the spectroscopic confirmation of the lowest energy computed structures.

FIFA määras Pohlaku ausa mängu komiteesse

Index Scriptorium Estoniae

2008-01-01

Vt. ka Linnaleht : Tartu 6. veebr., lk. 6. Maailma jalgpalliliite ühendav ja maailma jalgpallielu juhtiv FIFA määras Eesti Jalgpalli Liidu presidendi Aivar Pohlaku ausa mängu ja sotsiaalse vastutuse komitee liikmeks

m6A level and isoform characterization sequencing (m6A-LAIC-seq) reveals the census and complexity of the m6A epitranscriptome

OpenAIRE

Molinie, Benoit; Wang, Jinkai; Lim, Kok-Seong; Hillebrand, Roman; Lu, Zhi-xiang; Van Wittenberghe, Nicholas; Howard, Benjamin D.; Daneshvar, Kaveh; Mullen, Alan C.; Dedon, Peter; Xing, Yi; Giallourakis, Cosmas C.

2016-01-01

N6-Methyladenosine (m6A) is a widespread, reversible chemical modification of RNA molecules, implicated in many aspects of RNA metabolism. Little quantitative information exists as to either how many transcript copies of particular genes are m6A modified (‘m6A levels’) or the relationship of m6A modification(s) to alternative RNA isoforms. To deconvolute the m6A epitranscriptome, we developed m6A-level and isoform-characterization sequencing (m6A-LAIC-seq). We found that cells exhibit a broad...

The s-process enrichment of the globular clusters M4 and M22

Energy Technology Data Exchange (ETDEWEB)

Shingles, Luke J.; Karakas, Amanda I.; Fishlock, Cherie K.; Yong, David; Da Costa, Gary S.; Marino, Anna F. [Research School of Astronomy and Astrophysics, Australian National University, Canberra, ACT 2611 (Australia); Hirschi, Raphael, E-mail: luke.shingles@anu.edu.au [Institute for the Physics and Mathematics of the Universe (WPI), University of Tokyo, 5-1-5 Kashiwanoha, 277-8583 Kashiwa (Japan)

2014-11-01

We investigate the enrichment in elements produced by the slow neutron-capture process (s-process) in the globular clusters M4 (NGC 6121) and M22 (NGC 6656). Stars in M4 have homogeneous abundances of Fe and neutron-capture elements, but the entire cluster is enhanced in s-process elements (Sr, Y, Ba, Pb) relative to other clusters with a similar metallicity. In M22, two stellar groups exhibit different abundances of Fe and s-process elements. By subtracting the mean abundances of s-poor from s-rich stars, we derive s-process residuals or empirical s-process distributions for M4 and M22. We find that the s-process distribution in M22 is more weighted toward the heavy s-peak (Ba, La, Ce) and Pb than M4, which has been enriched mostly with light s-peak elements (Sr, Y, Zr). We construct simple chemical evolution models using yields from massive star models that include rotation, which dramatically increases s-process production at low metallicity. We show that our massive star models with rotation rates of up to 50% of the critical (break-up) velocity and changes to the preferred {sup 17}O(α, γ){sup 21}Ne rate produce insufficient heavy s-elements and Pb to match the empirical distributions. For models that incorporate asymptotic giant branch yields, we find that intermediate-mass yields (with a {sup 22}Ne neutron source) alone do not reproduce the light-to-heavy s-element ratios for M4 and M22, and that a small contribution from models with a {sup 13}C pocket is required. With our assumption that {sup 13}C pockets form for initial masses below a transition range between 3.0 and 3.5 M {sub ☉}, we match the light-to-heavy s-element ratio in the s-process residual of M22 and predict a minimum enrichment timescale of between 240 and 360 Myr. Our predicted value is consistent with the 300 Myr upper limit age difference between the two groups derived from isochrone fitting.

Scintigraphic findings on 99mTc-MDP, 99mTc-sestamibi and 99mTc-HMPAO images in Gaucher's disease

International Nuclear Information System (INIS)

Mariani, G.; Molea, N.; La Civita, L.; Porciello, G.; Lazzeri, E.; Ferri, C.

1996-01-01

We report here on the use of the lipophilic cationic complex technetium-99m sestamibi ( 99m Tc-MIBI), employed as an indicator of increased cellular density and metabolic activity, to evaluate Gaucher cell infiltrates in the bone marrow; 99m Tc-hexametazime ( 99m Tc-HMPAO) was also employed, as a pure indicator of lipidic infiltration in the bone marrow. A 67-year-old patient with known type 1 Gaucher's disease presented with a painful left hip and knee and difficulty in gait subsequent to traumatic fracture of the left femoral neck that had required implant of a fixation screw-plaque. Bone scan with 99m Tc-methylene diphosphonate revealed reduced uptake at the distal metaphyseal-epiphyseal femoral region. In addition, whole-body maps and spot-view acquisitions of the thighs and legs were recorded at both 30 min and 2.5 h after the injection of 99m Tc-MIBI: the scintigraphic pattern clearly showed increased uptake at several sites involved by Gaucher deposits in the bone marrow (both knees, with variable intensity in different areas), matching the bone changes detected by conventional x-ray. The target to non-target ratios slowly decreased with time, from an average value of 2.25 in the early scan to an average value of 2 in the delayed scan. The lipid-soluble agent 99m Tc-HMPAO exhibited a superimposable scintigraphic pattern of accumulation at the involved sites, though with lower target to non-target ratios (1.27-1.48). The results obtained in this patient suggest a potential role of 99m Tc-MIBI in the scintigraphic evaluation of Gaucher's lipid deposits in the bone marrow. If the results are confirmed in other patients, this radiopharmaceutical would offer clear advantages over 133 Xe because of its wider availability and greater practicality (i.v. administration of 99m Tc-MIBI versus inhalation of 133 Xe, and use of a single gamma camera instead of two as with 133 Xe). (orig.). With 3 figs

Structure and stability of M6N8 clusters (M = Si, Ge, Sn, Ti).

Science.gov (United States)

Davydova, Elena I; Timoshkin, Alexey Y; Frenking, Gernot

2010-06-10

The structures and stabilities of the M(6)N(8) clusters (M = Si, Ge, Sn, Ti) have been theoretically studied at DFT and ab initio levels of theory. Two new isomers have been considered: cage-like molecules and propeller-like molecules. It is shown that only for M = Si are both isomers true minima on the potential energy surface. The thermodynamics of the dissociation process (1/6)M(6)N(8) --> (1/3)M(3)N(4) is discussed. For each M(3)N(4) molecule, four structures with different multiplicity are considered. The thermodynamic analysis shows that independently of the multiplicity of M(3)N(4) nitrides all M(6)N(8) clusters are stable in the gas phase in a wide temperature range and could be potential intermediates in chemical vapor deposition of the nitride materials.

Evaluation of the absorbed dose to the kidneys due to Tc{sup 99m} (DTPA) / Tc{sup 99m} (Mag3) and Tc{sup 99m} (Dmsa); Evaluacion de la dosis absorbida en los rinones debido al Tc{sup 99m} (DTPA) / Tc{sup 99m} (MAG3) y Tc{sup 99m} (DMSA)

Energy Technology Data Exchange (ETDEWEB)

Vasquez A, M.; Murillo C, F.; Castillo D, C.; Rocha J, J.; Sifuentes D, Y.; Sanchez S, P. [Universidad Nacional de Trujillo, Av. Juan Pablo II s/n, Trujillo (Peru); Idrogo C, J.; Marquez P, F., E-mail: marvva@hotmail.com [Instituto Nacional de Enfermedades Neoplasicas, Av. Angamos 2520, Lima (Peru)

2015-10-15

The absorbed dose in the kidneys of adult patients has been assessed using the biokinetics of radiopharmaceuticals containing Tc{sup 99m} (DTPA) / Tc{sup 99m} (Mag3) or Tc{sup 99m} (Dmsa).The absorbed dose was calculated using the formalism MIRD and the Cristy-Eckerman representation for the kidneys. The absorbed dose to the kidneys due to Tc{sup 99m} (DTPA) / Tc{sup 99m} (Mag3), are given by 0.00466 mGy.MBq{sup -1} / 0.00339 mGy.MBq{sup -1}. Approximately 21.2% of the absorbed dose is due to the bladder (content) and the remaining tissue, included in biokinetics of Tc{sup 99m} (DTPA) / Tc{sup 99m} (Mag3). The absorbed dose to the kidneys due to Tc{sup 99m} (Dmsa) is 0.17881 mGy.MBq{sup -1}. Here, 1.7% of the absorbed dose is due to the bladder, spleen, liver and the remaining tissue, included in biokinetics of Tc{sup 99m} (Dmsa). (Author)

Otsitakse pilte Kalvi mõisast

Index Scriptorium Estoniae

2000-01-01

OÜ Kalwi Mõis otsib fotosid, maale, kirjeldusi ja mälestusi Kalvi mõisast ja selle ümbrusest, et neid kasutada mõisa restaureerimiseks ja mõisa ajalugu tutvustava muuseumitoa sisustamiseks; mõisa kavatsetakse rajada hotell, mille toad sisustataks ajaloolistes stiilides.

Thermal conductivity of M-Si-N (M = Mg, Ca, Sr, Ba) compounds with varying M/Si ratio

NARCIS (Netherlands)

Hintzen, H.T.J.M.; Bruls, R.J.; Delsing, A.C.A.; Itatani, K.; Tanaka, S.; With, de G.; Metselaar, R.

2002-01-01

The thermal cond. of M-Si-N (M = Mg, Ca, Sr, Ba) compds. was examd. The emphasis is on MgSiN2 (a material which can be derived from AlN by replacing systematically 2Al3+ by Mg2+/Si4+), and Si3N4 (the well known b-modification as well as the recently discovered cubic modification with the spinel

m6ASNP: a tool for annotating genetic variants by m6A function.

Science.gov (United States)

Jiang, Shuai; Xie, Yubin; He, Zhihao; Zhang, Ya; Zhao, Yuli; Chen, Li; Zheng, Yueyuan; Miao, Yanyan; Zuo, Zhixiang; Ren, Jian

2018-04-02

Large-scale genome sequencing projects have identified many genetic variants for diverse diseases. A major goal of these projects is to characterize these genetic variants to provide insight into their function and roles in diseases. N6-methyladenosine (m6A) is one of the most abundant RNA modifications in eukaryotes. Recent studies have revealed that aberrant m6A modifications are involved in many diseases. In this study, we present a user-friendly web server called "m6ASNP" that is dedicated to the identification of genetic variants targeting m6A modification sites. A random forest model was implemented in m6ASNP to predict whether the methylation status of a m6A site is altered by the variants surrounding the site. In m6ASNP, genetic variants in a standard VCF format are accepted as the input data, and the output includes an interactive table containing the genetic variants annotated by m6A function. In addition, statistical diagrams and a genome browser are provided to visualize the characteristics and annotate the genetic variants. We believe that m6ASNP is a highly convenient tool that can be used to boost further functional studies investigating genetic variants. The web server "m6ASNP" is implemented in JAVA and PHP and is freely available at http://m6asnp.renlab.org.

Irreducible kernels and nonperturbative expansions in a theory with pure m -> m interaction

International Nuclear Information System (INIS)

Iagolnitzer, D.

1983-01-01

Recent results on the structure of the S matrix at the m-particle threshold (m>=2) in a simplified m->m scattering theory with no subchannel interaction are extended to the Green function F on the basis of off-shell unitarity, through an adequate mathematical extension of some results of Fredholm theory: local two-sheeted or infinite-sheeted structure of F around s=(mμ) 2 depending on the parity of (m-1) (ν-1) (where μ>0 is the mass and ν is the dimension of space-time), off-shell definition of the irreducible kernel U [which is the analogue of the K matrix in the two different parity cases (m-1)(ν-1) odd or even] and related local expansion of F, for (m-1)(ν-1) even, in powers of sigmasup(β)lnsigma(sigma=(mμ) 2 -s). It is shown that each term in this expansion is the dominant contribution to a Feynman-type integral in which each vertex is a kernel U. The links between kernel U and Bethe-Salpeter type kernels G of the theory are exhibited in both parity cases, as also the links between the above expansion of F and local expansions, in the Bethe-Salpeter type framework, of Fsub(lambda) in terms of Feynman-type integrals in which each vertex is a kernel G and which include both dominant and subdominant contributions. (orig.)

M(II)-dipyridylamide-based coordination frameworks (M=Mn, Co, Ni): Structural transformation

Energy Technology Data Exchange (ETDEWEB)

Tzeng, Biing-Chiau; Selvam, TamilSelvi; Tsai, Miao-Hsin

2016-11-15

A series of 1-D double-zigzag (([M(papx){sub 2}(H{sub 2}O){sub 2}](ClO{sub 4}){sub 2}){sub n}; M=Mn, x=s (1), x=o (3); M=Co, x=s (4), x=o (5); M=Ni, x=s (6), x=o (7)) and 2-D polyrotaxane ([Mn(paps){sub 2}(ClO{sub 4}){sub 2}]{sub n} (2)) frameworks were synthesized by reactions of M(ClO{sub 4}){sub 2} (M=Mn, Co, and Ni) with papx (paps, N,N’-bis(pyridylcarbonyl)-4,4’-diaminodiphenylthioether; papo, N,N’-bis(pyridylcarbonyl)-4,4’-diaminodiphenyl ether), which have been isolated and structurally characterized by X-ray diffraction. Based on powder X-ray diffraction (PXRD) experiments, heating the double-zigzag frameworks underwent structural transformation to give the respective polyrotaxane ones. Moreover, grinding the solid samples of the respective polyrotaxanes in the presence of moisture also resulted in the total conversion to the original double-zigzag frameworks. In this study, we have successfully extended studies to Mn{sup II}, Co{sup II}, and Ni{sup II} frameworks from the previous Zn{sup II}, Cd{sup II}, and Cu{sup II} ones, and interestingly such structural transformation is able to be proven experimentally by powder and single-crystal X-ray diffraction studies as well. - Graphical abstract: 1-D double-zigzag and 2-D polyrotaxane frameworks of M(II)-papx (x=s, o; M=Mn, Co, Ni) frameworks can be interconverted by heating and grinding in the presence of moiture, and such structural transformation has be proven experimentally by powder and single-crystal X-ray diffraction studies.

Performance Analysis and Optimal Allocation of Layered Defense M/M/N Queueing Systems

Directory of Open Access Journals (Sweden)

Longyue Li

2016-01-01

Full Text Available One important mission of strategic defense is to develop an integrated layered Ballistic Missile Defense System (BMDS. Motivated by the queueing theory, we presented a work for the representation, modeling, performance simulation, and channels optimal allocation of the layered BMDS M/M/N queueing systems. Firstly, in order to simulate the process of defense and to study the Defense Effectiveness (DE, we modeled and simulated the M/M/N queueing system of layered BMDS. Specifically, we proposed the M/M/N/N and M/M/N/C queueing model for short defense depth and long defense depth, respectively; single target channel and multiple target channels were distinguished in each model. Secondly, we considered the problem of assigning limited target channels to incoming targets, we illustrated how to allocate channels for achieving the best DE, and we also proposed a novel and robust search algorithm for obtaining the minimum channel requirements across a set of neighborhoods. Simultaneously, we presented examples of optimal allocation problems under different constraints. Thirdly, several simulation examples verified the effectiveness of the proposed queueing models. This work may help to understand the rules of queueing process and to provide optimal configuration suggestions for defense decision-making.

SYNTHESIS AND CHARACTERIZATION OF NOVEL M(II) (M = Mn(II ...

African Journals Online (AJOL)

The coordination chemistry towards the M(II) metal centre (M = Mn, Ni, Cu or ... On continuing our work in the field of the synthesis of hydrazide ligand and the studies of ... The 1H and 13C NMR spectra of the Schiff base were recorded in CDCl3 on a ..... The octahedral geometry can be supported by the d–d transition bands ...

Dynamic RACH Partition for Massive Access of Differentiated M2M Services

Directory of Open Access Journals (Sweden)

Qinghe Du

2016-03-01

Full Text Available In machine-to-machine (M2M networks, a key challenge is to overcome the overload problem caused by random access requests from massive machine-type communication (MTC devices. When differentiated services coexist, such as delay-sensitive and delay-tolerant services, the problem becomes more complicated and challenging. This is because delay-sensitive services often use more aggressive policies, and thus, delay-tolerant services get much fewer chances to access the network. To conquer the problem, we propose an efficient mechanism for massive access control over differentiated M2M services, including delay-sensitive and delay-tolerant services. Specifically, based on the traffic loads of the two types of services, the proposed scheme dynamically partitions and allocates the random access channel (RACH resource to each type of services. The RACH partition strategy is thoroughly optimized to increase the access performances of M2M networks. Analyses and simulation demonstrate the effectiveness of our design. The proposed scheme can outperform the baseline access class barring (ACB scheme, which ignores service types in access control, in terms of access success probability and the average access delay.

γγ → M{sup +}M{sup -}(M = π, K) processes with twist-3 corrections in QCD

Energy Technology Data Exchange (ETDEWEB)

Wang, Cong [Southwest University, School of Physical Science and Technology, Chongqing (China); Chinese Academy of Sciences, State Key Laboratory of Theoretical Physics, Institute of Theoretical Physics, Beijing (China); Zhou, Ming-Zhen; Chen, Hong [Southwest University, School of Physical Science and Technology, Chongqing (China)

2017-04-15

We study the γγ → M{sup +}M{sup -}(M = π, K) processes with the contributions from the two-particle twist-2 and twist-3 distribution amplitudes of pion and kaon mesons on BHL prescription in the standard hard-scattering approach. The results show that the contributions from twist-3 parts are actually not power suppressed compared with the leading-twist contributions in the low energy region. The cross sections with twist-3 corrections agree well with the experimental data in the two-photon center-of-mass energy W > 2.8 GeV and we also predict the cross section ratio σ{sub 0}(K{sup +}K{sup -})/σ{sub 0}(π{sup +}π{sup -}), which is compatible with the experimental data from TPC and Belle. (orig.)

99mTc-EDTA and 99mTc-DTPA complexes as hydrological tracers

International Nuclear Information System (INIS)

Dominguez, J.; Borroto, J.; Nazco, J.; Perez, E.; Gamboa, R.; Cruz, J.

2002-01-01

The [ 99m Tc-DTPA] 2- and [ 99m Tc-EDTA] 1- were evaluated as radiotracers for short time hydrological studies. Their complex stability after labelling with 9.25 GBq of 99m Tc, the behaviour against pH variations, from 5 to 9, in simulated solutions and in natural river waters and the sorption of these compounds on the river sediments, were tested in laboratory experiments. Finally field double tracing experiments were carried out for each of labelling complexes and Rhodamine WT. From recovery calculations not losses of the 99m Tc activity were observed. The shape of the RTD curves of the [ 99m Tc-DTPA] 2- and [ 99m Tc-EDTA] 1 were quite similar to the Rhodamine Wt ones. May be concluded that both complexes behaved conservatively on the studied environmental conditions. (author)

Final report on bilateral comparison EURAMET.M.T-S3: Torque wrenches (10 N m - 1 kN m)

Science.gov (United States)

Röske, Dirk; Medina, Nieves

2011-01-01

A bilateral comparison from 10 N m up to 1000 N m has been carried out between Physikalisch-Technische Bundesanstalt (PTB) and Centro Español de Metrología (CEM) for reference torque wrenches calibrated according to DKD-R 3-7. The transfer standards have been two reference torque wrenches, 10 N m and 1000 N m respectively, that have been measured between November and December 2010. The results presented here demonstrate the metrological equivalence, within the quoted uncertainties, of both participant laboratories. Main text. To reach the main text of this paper, click on Final Report. Note that this text is that which appears in Appendix B of the BIPM key comparison database kcdb.bipm.org/. The final report has been peer-reviewed and approved for publication by EURAMET, according to the provisions of the CIPM Mutual Recognition Arrangement (MRA).

M-quasi-hyponormal composition operators

Directory of Open Access Journals (Sweden)

Pushpa R. Suri

1987-01-01

Full Text Available A necessary and sufficient condition is obtained for M-quasi-hyponormal composition operators. It has also been proved that the class of M-quasi-hyponormal composition operators coincides with the class of M-paranormal composition operators. Existence of M-hyponormal composition operators which are not hyponormal; and M-quasihyponormal composition operators which are not M-hyponormal and quasi-hyponormal are also shown.

El método analítico como método natural

OpenAIRE

Lopera Echavarría, Juan Diego; Ramírez Gómez, Carlos Arturo; Zuluaga Aristizábal, Marda Ucaris; Ortiz Vanegas, Jennifer

2010-01-01

Retomando la definición de análisis como la descomposición de un todo en sus elementos constitutivos para proceder a su comprensión y rearticulación, el presente artículo expone al método analítico como el método natural de los seres humanos, muestra sus relaciones con el método científico y explicita su vinculación íntima con la ética, en tanto hábito resultante de la incorporación de dicho método. Based on the definition of analysis like the decomposition of a whole in its constituent el...

Classification of acute myeloid leukemia subtypes M1, M2 and M3 using active contour without edge segmentation and momentum backpropagation artificial neural network

Directory of Open Access Journals (Sweden)

Harjoko Agus

2018-01-01

Full Text Available Acute Myeloid Leukemia (AML is a type of cancer which attacks white blood cells from myeloid. AML has eight subtypes, namely: M0, M1, M2, M3, M4, M5, M6, and M7. AML subtypes M1, M2 and M3 are affected by the same type of cells, myeloblast, making it needs more detailed analysis to distinguish. To overcome these obstacles, this research is applying digital image processing with Active Contour Without Edge (ACWE and Momentum Backpropagation artificial neural network for AML subtypes M1, M2 and M3 classification based on the type of the cell. Six features required as training parameters from every cell obtained by using feature extraction. The features are: cell area, perimeter, circularity, nucleus ratio, mean and standard deviation. The results show that ACWE can be used for segmenting white blood cells with 83.789% success percentage of 876 total cell objects. The whole AML slides had been identified according to the cell types predicted number through training with momentum backpropagation. Five times testing calibration with the best parameter generated averages value of 84.754% precision, 75.887% sensitivity, 95.090% specificity and 93.569% accuracy.

Density functional calculations on 13-atom Pd12M (M = Sc—Ni) bimetallic clusters

International Nuclear Information System (INIS)

Tang Chun-Mei; Chen Sheng-Wei; Zhu Wei-Hua; Tao Cheng-Jun; Zhang Ai-Mei; Gong Jiang-Feng; Zou Hua; Liu Ming-Yi; Zhu Feng

2012-01-01

The geometric structures, electronic and magnetic properties of the 3d transition metal doped clusters Pd 12 M (M = Sc—Ni) are studied using the semi-core pseudopots density functional theory. The groundstate geometric structure of the Pd 12 M cluster is probably of pseudoicosahedron. The I h -Pd 12 M cluster has the most thermodynamic stability in five different symmetric isomers. The energy gap shows that Pd 12 M cluster is partly metallic. Both the absolutely predominant metal bond and very weak covalent bond might exist in the Pd 12 M cluster. The magnetic moment of Pd 12 M varies from 0 to 5 μ B , implying that it has a potential application in new nanomaterials with tunable magnetic properties

Neelima M Deshpande

Indian Academy of Sciences (India)

Home; Journals; Resonance – Journal of Science Education. Neelima M Deshpande. Articles written in Resonance – Journal of Science Education. Volume 1 Issue 8 August 1996 pp 34-42 General Article. Questioning a Dogma - Do Bacteria Know When and to Mutate ? Milind G Watve Neelima M Deshpande.

M N Saha

Indian Academy of Sciences (India)

Home; Journals; Resonance – Journal of Science Education. M N Saha. Articles written in Resonance – Journal of Science Education. Volume 3 Issue 5 May 1998 pp 84-96 Classics. The Origin of Mass in Neutrons and Protons · M N Saha · More Details Fulltext PDF ...

The moment magnitude M w and the energy magnitude M e: common roots and differences

Science.gov (United States)

Bormann, Peter; di Giacomo, Domenico

2011-04-01

Starting from the classical empirical magnitude-energy relationships, in this article, the derivation of the modern scales for moment magnitude M w and energy magnitude M e is outlined and critically discussed. The formulas for M w and M e calculation are presented in a way that reveals, besides the contributions of the physically defined measurement parameters seismic moment M 0 and radiated seismic energy E S, the role of the constants in the classical Gutenberg-Richter magnitude-energy relationship. Further, it is shown that M w and M e are linked via the parameter Θ = log( E S/ M 0), and the formula for M e can be written as M e = M w + (Θ + 4.7)/1.5. This relationship directly links M e with M w via their common scaling to classical magnitudes and, at the same time, highlights the reason why M w and M e can significantly differ. In fact, Θ is assumed to be constant when calculating M w. However, variations over three to four orders of magnitude in stress drop Δ σ (as well as related variations in rupture velocity V R and seismic wave radiation efficiency η R) are responsible for the large variability of actual Θ values of earthquakes. As a result, for the same earthquake, M e may sometimes differ by more than one magnitude unit from M w. Such a difference is highly relevant when assessing the actual damage potential associated with a given earthquake, because it expresses rather different static and dynamic source properties. While M w is most appropriate for estimating the earthquake size (i.e., the product of rupture area times average displacement) and thus the potential tsunami hazard posed by strong and great earthquakes in marine environs, M e is more suitable than M w for assessing the potential hazard of damage due to strong ground shaking, i.e., the earthquake strength. Therefore, whenever possible, these two magnitudes should be both independently determined and jointly considered. Usually, only M w is taken as a unified magnitude in many

The lightest Higgs boson of mSUGRA, mGMSB and mAMSB at present and future colliders: observability and precision analyses

International Nuclear Information System (INIS)

Dedes, A.; Heinemeyer, S.; Su, S.; Weiglein, G.

2003-01-01

We investigate the physics of the lightest CP-even MSSM Higgs boson at the Tevatron, the LHC, a linear e + e - collider, a γγ collider and a μ + μ - collider. The analysis is performed in the three most prominent soft SUSY-breaking scenarios, mSUGRA, mGMSB and mAMSB. For all colliders the observability and parameter regions with suppressed production cross sections (compared to a SM Higgs boson with the same mass) are investigated. For the lepton and photon colliders the potential is analyzed of precision measurements of the branching ratios of the light CP-even Higgs boson for obtaining indirect bounds on the mass of the CP-odd Higgs boson and the high-energy parameters of the soft SUSY-breaking scenarios. In regions of the parameter space where the LHC can detect the heavy Higgs bosons, precision measurements of the properties of the light Higgs boson at the linear collider can provide valuable information for distinguishing between the mSUGRA, mGMSB and mAMSB scenarios

Ventilation system in the RA reactor building - design specifications; Sistem ventilacije u objektu 'RA' - Tehnicki opis

Energy Technology Data Exchange (ETDEWEB)

Badrljica, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1984-09-15

Protective role of the ventilation system of nuclear facilities involve construction of ventilation barriers which prevent release of radioactive particulates or gases, elimination od radioactive particulates and gases from the air which is released from contaminated zones into the reactor environment. Ventilation barriers are created by dividing the building into a number of ventilation zones with different sub pressure compared to the atmospheric pressure. The RA reactor building is divided into four ventilation zones. First zone is the zone of highest risk. It includes reactor core with horizontal experimental channels, underground rooms of the primary coolant system (D{sub 2}O), helium system, hot cells and the space above the the reactor core. Second zone is the reactor hall and the room for irradiated fuel storage. The third zone includes corridors in the basement, ground floor and first floor where the probability of contamination is small. The fourth zone includes the annex where the contamination risk is low. There is no have natural air circulation in the reactor building. Ventilators for air input and outlet maintain the sub pressure in the building (pressure lower than the atmospheric pressure). This prevents release of radioactivity into the atmosphere. Zastitne uloge ventilacionog sistema kod nuklearnih postrojenja obuhvataju formiranje ventilacionih barijera koje onemugucavaju sirenje radioaktivnih cestica ili gasova putem cirkulacije vazduha; eliminaciju radioaktivnih cestica i gasova iz vazduha koji se evakuise iz kontaminiranih prostora u okolinu reaktorskog postrojenja. Formiranje zastitnih ventilacionih barijera ostvaruje se obicno podelom unutrasnjosti objekta na vise ventilacionih zona razlicitih podpritisaka u odnosu na spoljni atmosferski pritisak. Celi prostor zgrade reaktora RA podeljen je u cetiri ventilacione zone. Prva zona je zona najveceg rizika, u koju spadaju reaktorsko jezgro sa horizontalnim eksperimentalnim kanalima, tehnoloske

Ultrasonic Water-Gap Measurements in MTR Fuel Elements; Mesure par Ultrasons des Espaces Intercalaires dans les Elements Combustibles des Reacteurs d'Essai de Materiaux; Izmereniya vodyanogo zazora v teplovydelyayushchikh ehlementakh dlya materialovedcheskogo reaktora s pomoshch'yu ul'trazvuka; Medicion Ultrasonica de la Capa de Agua en Elementos Combustibles para Reactores de Ensayo de Materiales

Energy Technology Data Exchange (ETDEWEB)

Deknock, R. [Metallurgy Department, S.C.K./C.E.N., Mol (Belgium)

1965-10-15

en un convertidor tiempo-tension con circuitos logicos transistorizados. El instrumento permite un ajuste continuo del cero para cualquier espesor-arbitrario de la capa de agua entre 2 y 4 mm, con lo cual posibilita un registro con el cero en el centro de la escala. Ademas, cualquier intervalo deseado de 100 {mu}m puede dar una tension estable de 1 V a la salida para accionar un registrador. Se puede medir facilmente cualquier variacion en el espesor del agua con una precision de 5 {mu}m. Se han medido con este metodo varios elementos combustibles, y los resultados y la reproducibilidad fueron muy satisfactorios. (author) [Russian] Sil'nye potoki teplo- vyh nejtronov, kotorye obychno voznikajut v novejshih reaktorah dlja ispytanija materialov, javljajutsja podhodjashhim s r e d s t v om ravnomernoj teploperedachi i nadezhnogo otvoda tepla, s pomoshh'ju kotorogo mozhno izbezhat' obrazovanija para v bol'shih ob{sup e}mah. Krome togo, v celjah kontrolja nad obshhim raspuhaniem i povedeniem reaktornogo topli- va izmerjajut vodjanoj zazor pri jeksperimentah posle obluchenija s otrabotannymi teplovy- deljajushhimi jelementami. S jetoj cel'ju byl razrabotan zond dlja izmerenija 3 - m m vodjanogo zazora teplovydeljaju- shhego jelementa ispytatel'nogo reaktora BR-2 dlinoj bolee 1 m , v osnovu kotorogo polozhen princip ul'trazvuka. Pri jeksperimentah posle obluchenija izmeritel'nyj zond dolzhen dej- stvovat' v teplovydeljajushhem jelemente, pogruzhennom v bassejn na glubinu ne menee 6 m . Zond mozhet vyderzhat' pogruzhenie v vodu prodolzhitel'nyj period vremeni, i on ne podver- gaetsja vozdejstviju obychnyh doz gamma-obluchenija. Hotja sistema dejstvuet na osnove obychnogo metoda otrazhenija impul'sov, ona pozvo- ljaet razdeljat' ispuskaemye i otrazhennye impul'sy s pomoshh'ju 10 Mgc ferrojelektriches- kogo kristalla, kotoromu svojstvenno bol'shoe rassejanie jenergii. Mozhno ispol'zovat' zapis' pokazanij oscilloskopa, v kotorom vremja registriruetsja na gorizontal'noj osi

Professor M. M. Zagorulko’s school of economic and military history of Russia

Directory of Open Access Journals (Sweden)

Redkina Olga Yurievna

2013-10-01

Full Text Available Maxim Matveyevich Zagorulko is the first rector of Volgograd State University, the veteran of the Great Patriotic War, the Honorable Citizen of Volgograd. He is the founder and the head of the scientific school studying various aspects of the Fatherland’s history. In the 1960s, M.M. Zagorulko united researches in the field of an economic history of Russia and the Great Patriotic War history. He had chosen as a subject of his doctoral dissertation a history of operation of economy of temporarily occupied territories of the USSR by fascists. In 1970, M.M. Zagorulko in a co-authorship with the Moscow scholar, the active participant of guerrilla movement A.F. Yudenkov published the monograph “Crash of Economic Plans of Fascist Germany on Temporarily Occupied Territory of the USSR”. Soon it was translated into the Czech language. In 1974, there was the second, added and modified edition of the book by M.M. Zagorulko and A.F. Yudenkov – “Crash of the «Oldenburg» Plan”. The third edition of this book was issued in 1980 in the Russian and Czech languages in Moscow and Bratislava. In 1975, Maxim M. Zagorulko defended his doctoral dissertation in the Dissertation Council of Leningrad State University on the subject “Economic Policy of Fascist Germany in the Occupied Territory of the USSR and Its Crash”. M.M. Zagorulko, his pupils and adherents conduct scientific researches in the field of an Economic History of Russia, History of military captivity in the USSR, History of the Battle of Stalingrad and so forth. Under his management multivolume collections of documents were published, monographs were written and dissertations were defended. The fundamental Encyclopedia of the Battle of Stalingrad created by him was declared in 2010 as “The best book of Russia”. In all these projects, theses and monographs M.M. Zagorulko is the organizer and inspirer of scientific researches.

M R Anantharaman

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. M R Anantharaman. Articles written in Bulletin of Materials Science. Volume 24 Issue 6 December 2001 pp 623-631 Magnetic Materials. Tailoring magnetic and dielectric properties of rubber ferrite composites containing mixed ferrites · M R Anantharaman K A Malini S Sindhu ...

Jasmine M Shah

Indian Academy of Sciences (India)

Home; Journals; Resonance – Journal of Science Education. Jasmine M Shah. Articles written in Resonance – Journal of Science Education. Volume 18 Issue 4 April 2013 pp 336-344 General Article. Glimpses of a Century-Old Story - Agrobacterium, a Pathogen Deployed for Genetic Engineering · Jasmine M Shah.

esraa m bakhsh

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. ESRAA M BAKHSH. Articles written in Bulletin of Materials Science. Volume 41 Issue 2 April 2018 pp 47. Assessment of cellulose acetate/manganese oxide thin film as adsorbent for selective extraction of flavone · EKRAM Y DANISH HADI M MARWANI MARYA A ALHAZMI ...

Effects of muscarinic receptor antagonists on cocaine discrimination in wild-type mice and in muscarinic receptor M1, M2, and M4 receptor knockout mice.

Science.gov (United States)

Joseph, Lauren; Thomsen, Morgane

2017-06-30

Muscarinic M 1 /M 4 receptor stimulation can reduce abuse-related effects of cocaine and may represent avenues for treating cocaine addiction. Muscarinic antagonists can mimic and enhance effects of cocaine, including discriminative stimulus (S D ) effects, but the receptor subtypes mediating those effects are not known. A better understanding of the complex cocaine/muscarinic interactions is needed to evaluate and develop potential muscarinic-based medications. Here, knockout mice lacking M 1 , M 2 , or M 4 receptors (M 1 -/- , M 2 -/- , M 4 -/- ), as well as control wild-type mice and outbred Swiss-Webster mice, were trained to discriminate 10mg/kg cocaine from saline. Muscarinic receptor antagonists with no subtype selectivity (scopolamine), or preferential affinity at the M 1 , M 2 , or M 4 subtype (telenzepine, trihexyphenidyl; methoctramine, AQ-RA 741; tropicamide) were tested alone and in combination with cocaine. In intact animals, antagonists with high affinity at M 1 /M 4 receptors partially substituted for cocaine and increased the S D effect of cocaine, while M 2 -preferring antagonists did not substitute, and reduced the S D effect of cocaine. The cocaine-like effects of scopolamine were absent in M 1 -/- mice. The cocaine S D attenuating effects of methoctramine were absent in M 2 -/- mice and almost absent in M 1 -/- mice. The findings indicate that the cocaine-like S D effects of muscarinic antagonists are primarily mediated through M 1 receptors, with a minor contribution of M 4 receptors. The data also support our previous findings that stimulation of M 1 receptors and M 4 receptors can each attenuate the S D effect of cocaine, and show that this can also be achieved by blocking M 2 autoreceptors, likely via increased acetylcholine release. Copyright © 2017 Elsevier B.V. All rights reserved.

Peynir Yapımında Mikrobiyal Renet Kullanımı

Directory of Open Access Journals (Sweden)

Mehmet Karapınar

2015-02-01

Full Text Available Peynir yapımında süt koagulantı olarak buzağı reneti yerine kullanılmak üzere proteazlar üzerine yapılan çalışmalar son yıllarda yoğunluk kazanmıştır. Günümüzde buzağı reneti standart bir süt koagulantı olarak önemini sürdürmekteyse de, şirden mayası üretimi her yıl giderek gereksinimi karşılayamaz duruma gelmektedir. Bunun sonucu olarak yeni renet kaynakları arasında yoğunlaşmış ve günümüzde Mucor pusillus, M. miehei, Endothia parasitica küf türlerinden elde edilen üç fungal enzim ile Bacillus cereus bakterisinden elde edilen bir bakteriyel enzim ticari olarak üretilmeye başlanmıştır.

The mutual dependence of M1 fertility and M2 mutations in rice

International Nuclear Information System (INIS)

Gopinathan Nair, V.

1982-01-01

The mutual dependence of M 1 fertility and M 2 mutations in rice was studied after treatment with gamma rays and EMS. The frequency of chlorophyll mutations increased with decrease in seed fertility when M 1 ears were selected at random. However, at the lowest fertility class the mutation frequency was low. This reduction is attributed to the elimination of mutants in the high sterility class. The mutation yield can therefore be significantly enhanced by selecting M 1 ears of low fertility. The segregation ratio of mutants increased as fertility decreased. Mutation spectrum was however not influenced by M 1 fertility. This makes selection for fertility quite ineffective in altering the mutation spectrum. (author)

Detailed profile of m=2 islands with TVTS on JFT-2M

International Nuclear Information System (INIS)

Yamauchi, T.; Grek, B.; Hoshino, K.; Le Blanc, B.; Johnson, D.; Felt, J.; Shiina, T.; Kurita, G.; Ishige, Y.; Kozawa, H.

1996-01-01

The detailed electron temperature profile (spatial resolution: 0.86 cm) of a low density JFT-2M plasma is measured with the TV Thomson scattering system (TVTS). Flat profiles showing the electron temperature shapes of m=2/n=1 islands are presented, which are in contrast to that without islands. On the other hand, the m=2/n=1 islands are effectively suppressed with local ECRH heating. (orig.)

Power Aware Mobility Management of M2M for IoT Communications

Directory of Open Access Journals (Sweden)

Awais Ahmad

2015-01-01

Full Text Available Machine-to-Machine (M2M communications framework is evolving to sustain faster networks with the potential to connect millions of devices in the following years. M2M is one of the essential competences for implementing Internet of Things (IoT. Therefore, various organizations are now focusing on enhancing improvements into their standards to support M2M communications. Thus, Heterogeneous Mobile Ad Hoc Network (HetMANET can normally be considered appropriate for M2M challenges. These challenges incorporated when a mobile node (MN selects a target network in an energy efficient scanning for efficient handover. Therefore, to cope with these constraints, we proposed a vertical handover scheme for handover triggering and selection of an appropriate network. The proposed scheme is composed of two phases. Firstly, the MNs perform handover triggering based on the optimization of the Receive Signal Strength (RSS from an access point/base station (AP/BS. Secondly, the network selection process is performed by considering the cost and energy consumption of a particular application during handover. Moreover, if there are more networks available, then the MN selects the one provided with the highest quality of service (QoS. The decision regarding the selection of available networks is made on three metrics, that is, cost, energy, and data rate. Furthermore, the selection of an AP/BS of the selected network is made on five parameters: delay, jitter, Bit Error Rate (BER, communication cost, and response time. The numerical and experimental results are compared in the context of energy consumption by an MN, traffic management on an AP/BS, and QoS of the available networks. The proposed scheme efficiently optimizes the handoff related parameters, and it shows significant improvement in the existing models used for similar purpose.

Evaluation of secure capability-based access control in the M2M local cloud platform

DEFF Research Database (Denmark)

Anggorojati, Bayu; Prasad, Neeli R.; Prasad, Ramjee

2016-01-01

delegation. Recently, the capability based access control has been considered as method to manage access in the Internet of Things (IoT) or M2M domain. In this paper, the implementation and evaluation of a proposed secure capability based access control in the M2M local cloud platform is presented......Managing access to and protecting resources is one of the important aspect in managing security, especially in a distributed computing system such as Machine-to-Machine (M2M). One such platform known as the M2M local cloud platform, referring to BETaaS architecture [1], which conceptually consists...... of multiple distributed M2M gateways, creating new challenges in the access control. Some existing access control systems lack in scalability and flexibility to manage access from users or entity that belong to different authorization domains, or fails to provide fine grained and flexible access right...

Superplastic deformation of P/M and I/M Al-Li based alloys

International Nuclear Information System (INIS)

Lederich, R.J.; Sastry, S.M.L.

1984-01-01

Incremental strain-rate and constant strain-rate cone-forming tests have been carried out at 450-550 C to investigate the superplastic forming characteristics of Al-Li-Cu-Mn, Al-Li-Cu-Mg-Zr, and Al-Li-Zn-Mg alloys processed by powder-metallurgy (P/M) and ingot-metallurgy (I/M) techniques. It is found that P/M Al-Li alloys containing 0.2 pct Zr are inherently superplastically formable without the need for extensive thermomechanical processing. I/M Al-Li alloys containing Zr are also superplastically formable. The mechanical properties of the superplastically formed and solution-treated-and-aged alloys are comparable to those of solution-treated-and-aged alloys before superplastic forming. 6 references

hadi m marwani

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. HADI M MARWANI. Articles written in Bulletin of Materials Science. Volume 39 Issue 4 August 2016 pp 1011-1019. Selective extraction and detection of noble metal based on ionic liquid immobilized silica gel surface using ICP-OES · HADI M MARWANI AMJAD E ALSAFRANI ...

Nirendra M Misra

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. Nirendra M Misra. Articles written in Bulletin of Materials Science. Volume 33 Issue 2 April 2010 pp 165-168 Polymers. Thermal stability of PMMA–clay hybrids · Tanushree Choudhury Nirendra M Misra · More Details Abstract Fulltext PDF. Materials with small particle size are ...

M Harish Bhat

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. M Harish Bhat. Articles written in Bulletin of Materials Science. Volume 23 Issue 6 December 2000 pp 461-466 Material Synthesis. Microwave synthesis of electrode materials for lithium batteries · M Harish Bhat B P Chakravarthy P A Ramakrishnan A Levasseur K J RAO.

Mary M Mader

Indian Academy of Sciences (India)

Home; Journals; Resonance – Journal of Science Education. Mary M Mader. Articles written in Resonance – Journal of Science Education. Volume 2 Issue 1 January 1997 pp 53-59 General Article. Fostering Creativity in Students A Short Synthesis Project for the Organic Chemistry Laboratory · Mary M Mader Charles A ...

Jayant M Modak

Indian Academy of Sciences (India)

Home; Journals; Resonance – Journal of Science Education. Jayant M Modak. Articles written in Resonance – Journal of Science Education. Volume 7 Issue 9 September 2002 pp 69-77 General Article. Haber Process for Ammonia Synthesis · Jayant M Modak · More Details Fulltext PDF. Volume 16 Issue 12 December ...

M R Sudarsana Kumar

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. M R Sudarsana Kumar. Articles written in Bulletin of Materials Science. Volume 24 Issue 2 April 2001 pp 249-252 Crystal Growth. Thermal behaviour of strontium tartrate single crystals grown in gel · M H Rahimkutty K Rajendra Babu K Sreedharan Pillai M R Sudarsana Kumar ...

99mTc-MIBI, 99mTc-tetrofosmin and 99mTc-Q12 in vitro and in vivo

International Nuclear Information System (INIS)

Bernard, Bert F.; Krenning, Eric P.; Breeman, Wout A. P.; Ensing, Geert; Benjamins, Harry; Bakker, Willem H.; Visser, Theo J.; Jong, Marion de

1998-01-01

The aim of this study was to compare uptake of 99m Tc-MIBI, 99m Tc-tetrofosmin and 99m Tc-Q12 in vitro and biodistribution in vivo in rats. In vitro, uptake decreased in the order MIBI→tetrofosmin→Q12. Uptake of MIBI and tetrofosmin, but not of Q12, in cultured tumor cells was dependent on the plasma membrane and mitochondrial potential. In vivo, heart uptake of all three compounds was high and stable. Tumor uptake decreased in the order MIBI→Q12→tetrofosmin and the tumor/blood ratio in the order MIBI→tetrofosmin→Q12

Aggregation and Trunking of M2M Traffic via D2D Connections

DEFF Research Database (Denmark)

Rigazzi, Giovanni; Kiilerich Pratas, Nuno; Popovski, Petar

2015-01-01

Machine-to-Machine (M2M) communications is one of the key enablers of the Internet of Things (IoT). Billions of devices are expected to be deployed in the near future for novel M2M applications demanding ubiquitous access and global connectivity. In order to cope with the massive number of machines......, there is a need for new techniques to coordinate the access and allocate the resources. Although the majority of the proposed solutions are focused on the adaptation of the traditional cellular networks to the M2M traffic patterns, novel approaches based on the direct communication among nearby devices may...... represent an effective way to avoid access congestion and cell overload. In this paper, we propose a new strategy inspired by the classical Trunked Radio Systems (TRS), exploiting the Device-to-Device (D2D) connectivity between cellular users and Machine-Type Devices (MTDs). The aggregation of the locally...

S M Kulkarni

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. S M Kulkarni. Articles written in Bulletin of Materials Science. Volume 25 Issue 2 April 2002 pp 137-140 Composites. Analysis of filler--fibre interaction in fly ash filled short fibre-epoxy composites using ultrasonic NDE · S M Kulkarni D Anuradha C R L Murthy Kishore.

M S Datta

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. M S Datta. Articles written in Bulletin of Materials Science. Volume 25 Issue 2 April 2002 pp 121-125 Ceramic Materials. Sintering of nano crystalline silicon carbide doping with aluminium nitride · M S Datta A K Bandyopadhyay B Chaudhuri · More Details Abstract Fulltext ...

A M Umarji

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. A M Umarji. Articles written in Bulletin of Materials Science. Volume 23 Issue 4 August 2000 pp 243-248 Refractory Cements. Ceramic joining through reactive wetting of alumina with calcium aluminate refractory cements · K Geetha A M Umarji T R N Kutty · More Details ...

G M Kalamse

Indian Academy of Sciences (India)

Home; Journals; Journal of Chemical Sciences. G M Kalamse. Articles written in Journal of Chemical Sciences. Volume 117 Issue 6 November 2005 pp 673-676. Dielectric studies of binary mixtures of -propyl alcohol and ethylenediamine · B S Narwade P G Gawali Rekha Pande G M Kalamse · More Details Abstract ...

M K Jayaraj

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. M K Jayaraj. Articles written in Bulletin of Materials Science. Volume 25 Issue 3 June 2002 pp 227-230 Thin Films. Transparent conducting zinc oxide thin film prepared by off-axis rf magnetron sputtering · M K Jayaraj Aldrin Antony Manoj Ramachandran · More Details Abstract ...

M Suresh Babu

Indian Academy of Sciences (India)

Home; Journals; Resonance – Journal of Science Education. M Suresh Babu. Articles written in Resonance – Journal of Science Education. Volume 7 Issue 3 March 2002 pp 18-24 General Article. Operating Systems - Objectives and Evolution · M Suresh Babu · More Details Fulltext PDF. Volume 7 Issue 4 April 2002 pp ...

Industry 4.0, M2m, Iot&S - All Equal?

Science.gov (United States)

Dobrin, Carmen

2014-11-01

Similarity between Industry 4.0, M2M, IOT&S. Advantages and disadvantages obtained using this three important methods. Decreasing costs while components are getting smaller and smaller in a world with better networking. Influence of business management applications integrated in smart factory logistic. The most important impacts in merging virtual and real production world, with the improvement of best processes having the same goal: creating value by open innovation

Technical realisation of the VISA-II Project, Phase II, Chapter X, Vol. VI; Tehnicka realizacija projekta VISA-II, II faza, Glava X, Album VI

Energy Technology Data Exchange (ETDEWEB)

Pavicevic, M; Nikolic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1963-01-15

The second phase of the 'Project VISA-2 described in this chapter of Vol. VI includes the project specifications and technical drawings of the 'measuring system of VISA-2 for testing the VISA-2 channels outside and in the reactor'. In addition to the task objective, description of the measuring system, action plan, description of the work done it contains the definition of the task 'Leak testing' and instructions for the instrumentation personnel on duty. [Serbo-Croat] Druga faza zadatka {sup T}ehnicka realizacija projekta VISA-2' opisana u ovom poglavlju Albuma VI, sadrzi tehnicki opis i crteze 'Mernog sistema VISA-2 i ispitivanje kanala VISA-2 van reaktora i u reaktoru'. Pored definicije zadatka, opisa mernog sistema VISA-2, razrade zadatka, tekstualnog dela projekta i opisa izvedenih radova, ovo poglavlje obuhvata definiciju i razradu podzadatka 'Ispitivanje hermeticnosti' i dodatak sa instrukcijama za dezurne instrumentatore u vezi eksperimenta VISA-2.

Operation and maintenance of the RA reactor; Pogon i odrzavanje reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Petrovic, M; Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1961-12-15

During 1961 the RA reactor was used for irradiation of samples for 258 users ( from which 188 from the Institute) and for 34 experiments, this means productions of 5958 MWh. The production was almost four times bigger than during previous year due to the demand of the Laboratories of the Institute. Burnup of the fuel from the first batch was about 30%. This means that the operation time could be much higher. Number of safety shut-downs was 11. The reasons were related to electrical faults, 9 occurrences, failure of the instrument for reactor period measurement, once, and failure of the pump once. This report covers state and operation data of the reactor components, control instruments, devices for reactor protection, dosimetry, heavy water system, helium system, mechanical and electrical equipment. Problems related to training of the staff and lack of personnel are mentioned as well.

Maximum neutron flux in thermal reactors; Maksimum neutronskog fluksa kod termalnih reaktora

Energy Technology Data Exchange (ETDEWEB)

Strugar, P V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

1968-07-01

Direct approach to the problem is to calculate spatial distribution of fuel concentration if the reactor core directly using the condition of maximum neutron flux and comply with thermal limitations. This paper proved that the problem can be solved by applying the variational calculus, i.e. by using the maximum principle of Pontryagin. Mathematical model of reactor core is based on the two-group neutron diffusion theory with some simplifications which make it appropriate from maximum principle point of view. Here applied theory of maximum principle are suitable for application. The solution of optimum distribution of fuel concentration in the reactor core is obtained in explicit analytical form. The reactor critical dimensions are roots of a system of nonlinear equations and verification of optimum conditions can be done only for specific examples.

Temperature reactivity coefficient of the RA reactor; Temperaturni koeficijenat reaktivnosti reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Raisic, N; Strugar, P; Dobrosavljevic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1961-12-15

Temperature reactivity coefficient of the RA reactor was determined as follows. Stabilization of moderator temperature and graphite reflector was achieved in the reactor operated at power levels of 20, 100, 500, 1000, 3000 and 5000 kW. Temperature change of the moderator was achieved by changing the water flow rate in the secondary cooling system. The fuel temperature was changed simultaneously. During the measurement at each power level the temperature change was between 30 - 50 deg C. Changing the position of the automated regulator is registered during moderator temperature change, and these changes were used for determining the total reactivity change by using the calibration curves for the automated regulator. In the measured temperature range the the reactivity change was linear and it was possible to determine the total temperature coefficient.

Almost optimal distributed M2M multicasting in wireless mesh networks

DEFF Research Database (Denmark)

Xin, Qin; Manne, Fredrik; Zhang, Yan

2012-01-01

Wireless Mesh Networking (WMN) is an emerging communication paradigm to enable resilient, cost-efficient and reliable services for the future-generation wireless networks. In this paper, we study the problem of multipoint-to- multipoint (M2M) multicasting in a WMN which aims to use the minimum nu...

Towards Efficient Mobile M2M Communications: Survey and Open Challenges

Directory of Open Access Journals (Sweden)

Carlos Pereira

2014-10-01

Full Text Available Machine-to-Machine (M2M communications enable networked devices and services to exchange information and perform actions seamlessly without the need for human intervention. They are viewed as a key enabler of the Internet of Things (IoT and ubiquitous applications, like mobile healthcare, telemetry, or intelligent transport systems. We survey existing work on mobile M2M communications, we identify open challenges that have a direct impact on performance and resource usage efficiency, especially the impact on energy efficiency, and we review techniques to improve communications. We review the ETSI standard and application protocols, and draw considerations on the impact of their use in constrained mobile devices. Nowadays, smartphones are equipped with a wide range of embedded sensors, with varied local and wide area connectivity capabilities, and thus they offer a unique opportunity to serve as mobile gateways for other more constrained devices with local connectivity. At the same time, they can gather context data about users and environment from the embedded sensors. These capabilities may be crucial for mobile M2M applications. Finally, in this paper, we consider a scenario where smartphones are used as gateways that collect and aggregate data from sensors in a cellular network. We conclude that, in order for their use to the feasible in terms of a normal depletion time of a smartphone’s battery, it is a good advice to maximize the collection of data necessary to be transmitted from nearby sensors, and maximize the intervals between transmissions. More research is required to devise energy efficient transmission methods that enable the use of smartphones as mobile gateways.

Towards efficient mobile M2M communications: survey and open challenges.

Science.gov (United States)

Pereira, Carlos; Aguiar, Ana

2014-10-20

Machine-to-Machine (M2M) communications enable networked devices and services to exchange information and perform actions seamlessly without the need for human intervention. They are viewed as a key enabler of the Internet of Things (IoT) and ubiquitous applications, like mobile healthcare, telemetry, or intelligent transport systems. We survey existing work on mobile M2M communications, we identify open challenges that have a direct impact on performance and resource usage efficiency, especially the impact on energy efficiency, and we review techniques to improve communications. We review the ETSI standard and application protocols, and draw considerations on the impact of their use in constrained mobile devices. Nowadays, smartphones are equipped with a wide range of embedded sensors, with varied local and wide area connectivity capabilities, and thus they offer a unique opportunity to serve as mobile gateways for other more constrained devices with local connectivity. At the same time, they can gather context data about users and environment from the embedded sensors. These capabilities may be crucial for mobile M2M applications. Finally, in this paper, we consider a scenario where smartphones are used as gateways that collect and aggregate data from sensors in a cellular network. We conclude that, in order for their use to the feasible in terms of a normal depletion time of a smartphone's battery, it is a good advice to maximize the collection of data necessary to be transmitted from nearby sensors, and maximize the intervals between transmissions. More research is required to devise energy efficient transmission methods that enable the use of smartphones as mobile gateways.

M D Subash Chandran

Indian Academy of Sciences (India)

M D Subash Chandran · More Details Fulltext PDF. Volume 4 Issue 10 October 1999 pp 69-77 Classroom. Project Lifescape – Flowering Plants · M D Subash Chandran V V Sivan · More Details Fulltext PDF. Volume 7 Issue 11 November 2002 pp 80-81 Book Review. Ecology and Sustainable Development · M D Subash ...

M Geetha Priya

Indian Academy of Sciences (India)

Home; Journals; Sadhana. M Geetha Priya. Articles written in Sadhana. Volume 38 Issue 4 August 2013 pp 645-651. A new universal gate for low power SoC applications · M Geetha Priya K Baskaran · More Details Abstract Fulltext PDF. This paper formulates a new design technique for an area and energy efficient ...

M S Narasimhan

Indian Academy of Sciences (India)

Home; Journals; Resonance – Journal of Science Education. M S Narasimhan. Articles written in Resonance – Journal of Science Education. Volume 15 Issue 2 February 2010 pp 101-101 Article-in-a-Box. Reminiscences · M S Narasimhan · More Details Fulltext PDF. Volume 20 Issue 6 June 2015 pp 483-490 General ...

M S Swaminathan

Indian Academy of Sciences (India)

M S Swaminathan. Articles written in Resonance – Journal of Science Education. Volume 15 Issue 7 July 2010 pp 675-677 Book Review. Remembering Sir J. C. Bose · M S Swaminathan · More Details Fulltext PDF. Volume 19 Issue 2 February 2014 pp 109-115 General Article. Norman Borlaug and a Hunger-Free World.

ISOMP: An Instant Service-Orchestration Mobile M2M Platform

Directory of Open Access Journals (Sweden)

Cholhong Im

2016-01-01

Full Text Available Smartphones have greater computing power than ever before, providing convenient applications to improve our lives. In general, people find it difficult to locate suitable applications and implementing new applications often requires professional skills. In this paper, we propose a new service platform that facilitates the implementation of new applications by composing prebuilt components that provide the context information of mobile devices such as location and contacts. Our platform introduces an innovative concept named context collaboration, in which smartphones exchange context information with each other, which in turn is used to deduct useful inferences. The concept is realized by instant orchestration, which assembles some components and implements a composite component. The interactive communication interface helps a mobile device to communicate with other devices using open APIs, such as SOAP and HTTP (REST. The platform also works in heterogeneous environments, for example, between Android and iOS operating systems. Throughout the platform, mobile devices can act as smart M2M machines with context awareness, enabling intelligent tasks on behalf of users. Our platform will open up a new and innovative pathway for both enhanced mobile context awareness and M2M, which is expected to be a fundamental feature of the next generation of mobile devices.

Macrophage polarisation: an immunohistochemical approach for identifying M1 and M2 macrophages.

Directory of Open Access Journals (Sweden)

Mário Henrique M Barros

Full Text Available Macrophage polarization is increasingly recognised as an important pathogenetic factor in inflammatory and neoplastic diseases. Proinflammatory M1 macrophages promote T helper (Th 1 responses and show tumoricidal activity. M2 macrophages contribute to tissue repair and promote Th2 responses. CD68 and CD163 are used to identify macrophages in tissue sections. However, characterisation of polarised macrophages in situ has remained difficult. Macrophage polarisation is regulated by transcription factors, pSTAT1 and RBP-J for M1, and CMAF for M2. We reasoned that double-labelling immunohistochemistry for the detection of macrophage markers together with transcription factors may be suitable to characterise macrophage polarisation in situ. To test this hypothesis, we have studied conditions associated with Th1- and Th2-predominant immune responses: infectious mononucleosis and Crohn's disease for Th1 and allergic nasal polyps, oxyuriasis, wound healing and foreign body granulomas for predominant Th2 response. In all situations, CD163+ cells usually outnumbered CD68+ cells. Moreover, CD163+ cells, usually considered as M2 macrophages, co-expressing pSTAT1 and RBP-J were found in all conditions examined. The numbers of putative M1 macrophages were higher in Th1- than in Th2-associated diseases, while more M2 macrophages were seen in Th2- than in Th1 related disorders. In most Th1-related diseases, the balance of M1 over M2 cells was shifted towards M1 cells, while the reverse was observed for Th2-related conditions. Hierarchical cluster analysis revealed two distinct clusters: cluster I included Th1 diseases together with cases with high numbers of CD163+pSTAT1+, CD68+pSTAT1+, CD163+RBP-J+ and CD68+RBP-J+ macrophages; cluster II comprised Th2 conditions together with cases displaying high numbers of CD163+CMAF+ and CD68+CMAF+ macrophages. These results suggest that the detection of pSTAT1, RBP-J, and CMAF in the context of CD68 or CD163 expression is a

Macrophage polarisation: an immunohistochemical approach for identifying M1 and M2 macrophages.

Science.gov (United States)

Barros, Mário Henrique M; Hauck, Franziska; Dreyer, Johannes H; Kempkes, Bettina; Niedobitek, Gerald

2013-01-01

Macrophage polarization is increasingly recognised as an important pathogenetic factor in inflammatory and neoplastic diseases. Proinflammatory M1 macrophages promote T helper (Th) 1 responses and show tumoricidal activity. M2 macrophages contribute to tissue repair and promote Th2 responses. CD68 and CD163 are used to identify macrophages in tissue sections. However, characterisation of polarised macrophages in situ has remained difficult. Macrophage polarisation is regulated by transcription factors, pSTAT1 and RBP-J for M1, and CMAF for M2. We reasoned that double-labelling immunohistochemistry for the detection of macrophage markers together with transcription factors may be suitable to characterise macrophage polarisation in situ. To test this hypothesis, we have studied conditions associated with Th1- and Th2-predominant immune responses: infectious mononucleosis and Crohn's disease for Th1 and allergic nasal polyps, oxyuriasis, wound healing and foreign body granulomas for predominant Th2 response. In all situations, CD163+ cells usually outnumbered CD68+ cells. Moreover, CD163+ cells, usually considered as M2 macrophages, co-expressing pSTAT1 and RBP-J were found in all conditions examined. The numbers of putative M1 macrophages were higher in Th1- than in Th2-associated diseases, while more M2 macrophages were seen in Th2- than in Th1 related disorders. In most Th1-related diseases, the balance of M1 over M2 cells was shifted towards M1 cells, while the reverse was observed for Th2-related conditions. Hierarchical cluster analysis revealed two distinct clusters: cluster I included Th1 diseases together with cases with high numbers of CD163+pSTAT1+, CD68+pSTAT1+, CD163+RBP-J+ and CD68+RBP-J+ macrophages; cluster II comprised Th2 conditions together with cases displaying high numbers of CD163+CMAF+ and CD68+CMAF+ macrophages. These results suggest that the detection of pSTAT1, RBP-J, and CMAF in the context of CD68 or CD163 expression is a suitable tool for

Predictions for m{sub t} and M{sub W} in minimal supersymmetric models

Energy Technology Data Exchange (ETDEWEB)

Buchmueller, O. [Imperial College, London (United Kingdom). High Energy Physics Group; Cavanaugh, R. [Fermi National Accelerator Lab., Batavia, IL (United States); Illinois Univ., Chicago, IL (United States). Dept. of Physics; Roeck, A. de [European Lab. for Particle Physics (CERN), Geneva (Switzerland); Universitaire Instelling Antwerpen, Wilrijk (Belgium); Ellis, J.R. [European Lab. for Particle Physics (CERN), Geneva (Switzerland); Flaecher, H. [Rochester Univ., NY (United States). Dept. of Physics and Astronomy; Heinemeyer, S. [Instituto de Fisica de Cantabria, Santander (Spain); Isidori, G. [INFN, Laboratori Nazionali di Frascati (Italy); Technische Univ. Muenchen (Germany). Inst. for Advanced Study; Olive, K.A. [Minnesota Univ., Minnesota, MN (United States). William I. Fine Theoretical Physics Institute; Ronga, F.J. [ETH Zuerich (Switzerland). Institute for Particle Physics; Weiglein, G. [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany)

2009-12-15

Using a frequentist analysis of experimental constraints within two versions of the minimal supersymmetric extension of the Standard Model, we derive the predictions for the top quark mass, m{sub t}, and the W boson mass, m{sub W}. We find that the supersymmetric predictions for both m{sub t} and m{sub W}, obtained by incorporating all the relevant experimental information and state-of-the-art theoretical predictions, are highly compatible with the experimental values with small remaining uncertainties, yielding an improvement compared to the case of the Standard Model. (orig.)

Transient analysis of an M/M/1 queue with multiple vacations

Directory of Open Access Journals (Sweden)

Kaliappan Kalidass

2014-05-01

Full Text Available In this paper, we have obtained explicit expressions for the time dependent probabilities of the M/M/1  queue with server vacations under a multiple vacation scheme. The corresponding steady state probabilities have been obtained. We also obtain the time dependent performance measures of the systems

Sequence spaces M ( ϕ $M(\\phi$ and N ( ϕ $N(\\phi$ with application in clustering

Directory of Open Access Journals (Sweden)

Mohd Shoaib Khan

2017-03-01

Full Text Available Abstract Distance measures play a central role in evolving the clustering technique. Due to the rich mathematical background and natural implementation of l p $l_{p}$ distance measures, researchers were motivated to use them in almost every clustering process. Beside l p $l_{p}$ distance measures, there exist several distance measures. Sargent introduced a special type of distance measures m ( ϕ $m(\\phi$ and n ( ϕ $n(\\phi$ which is closely related to l p $l_{p}$ . In this paper, we generalized the Sargent sequence spaces through introduction of M ( ϕ $M(\\phi$ and N ( ϕ $N(\\phi$ sequence spaces. Moreover, it is shown that both spaces are BK-spaces, and one is a dual of another. Further, we have clustered the two-moon dataset by using an induced M ( ϕ $M(\\phi$ -distance measure (induced by the Sargent sequence space M ( ϕ $M(\\phi$ in the k-means clustering algorithm. The clustering result established the efficacy of replacing the Euclidean distance measure by the M ( ϕ $M(\\phi$ -distance measure in the k-means algorithm.

A SPECTROSCOPIC SURVEY OF MASSIVE STARS IN M31 AND M33

Energy Technology Data Exchange (ETDEWEB)

Massey, Philip; Neugent, Kathryn F.; Smart, Brianna M., E-mail: phil.massey@lowell.edu, E-mail: kneugent@lowell.edu, E-mail: bsmart@astro.wisc.edu [Lowell Observatory, 1400 W Mars Hill Road, Flagstaff, AZ 86001 (United States)

2016-09-01

We describe our spectroscopic follow-up to the Local Group Galaxy Survey (LGGS) photometry of M31 and M33. We have obtained new spectroscopy of 1895 stars, allowing us to classify 1496 of them for the first time. Our study has identified many foreground stars, and established membership for hundreds of early- and mid-type supergiants. We have also found nine new candidate luminous blue variables and a previously unrecognized Wolf–Rayet star. We republish the LGGS M31 and M33 catalogs with improved coordinates, and including spectroscopy from the literature and our new results. The spectroscopy in this paper is responsible for the vast majority of the stellar classifications in these two nearby spiral neighbors. The most luminous (and hence massive) of the stars in our sample are early-type B supergiants, as expected; the more massive O stars are more rare and fainter visually, and thus mostly remain unobserved so far. The majority of the unevolved stars in our sample are in the 20–40 M {sub ⊙} range.

M Abdul Khadar

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. M Abdul Khadar. Articles written in Bulletin of Materials Science. Volume 23 Issue 5 October 2000 pp 361-367 Nanomaterials. Dielectric properties of nanophase Ag2HgI4 and Ag2HgI4–Al2O3 nanocomposites · S Sankara Narayanan Potty M Abdul Khadar · More Details ...

C M Dudhe

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. C M Dudhe. Articles written in Bulletin of Materials Science. Volume 38 Issue 5 September 2015 pp 1423-1427. Nucleation and evaporation of domains due to electric field at room temperature in BaTiO3 single crystals · C M Dudhe P R Arjunwadkar · More Details Abstract ...

G M Moremedi

Indian Academy of Sciences (India)

Home; Journals; Pramana – Journal of Physics. G M Moremedi. Articles written in Pramana – Journal of Physics. Volume 77 Issue 3 September 2011 pp 493-507. Effects of non-uniform interfacial tension in small Reynolds number flow past a spherical liquid drop · D P Mason G M Moremedi · More Details Abstract Fulltext ...

M G Narasimhan

Indian Academy of Sciences (India)

Volume 2 Issue 2 February 1997 pp 4-4 Article-in-a-Box. The Popper-Kuhn Debate on the Nature of Scientific Development · M G Narasimhan · More Details Fulltext PDF. Volume 16 Issue 6 June 2011 pp 529-539 General Article. Kosambi's Vision of Science - A Critical Appreciation · M G Narasimhan · More Details Fulltext ...

B M Pathan

Indian Academy of Sciences (India)

Home; Journals; Journal of Earth System Science. B M Pathan. Articles written in Journal of Earth System Science. Volume 114 Issue 2 April 2005 pp 177-184. IMF BY dependence of the extent of substorm westward electrojet · T Arun Ajay Dhar K Emperumal B M Pathan · More Details Abstract Fulltext PDF. In this paper the ...

Theoretical study of isoelectronic SinM clusters (M=Sc-,Ti,V+; n=14-18)

DEFF Research Database (Denmark)

Torres, M. B.; Fernandez Sanchez, Eva; Balbás, L. C.

2007-01-01

We study, from first-principles quantum mechanical calculations, the structural and electronic properties of several low-lying energy equilibrium structures of isoelectronic SinM clusters (M=Sc-,Ti,V+) for n=14-18. The main result is that those clusters with n=16 are more stable than its neighbors...... of the spherical potential model). The structures of the two lowest energy isomers of Si16M are nearly degenerate, and consist of the Frank-Kasper polyhedron and a distortion of that polyhedron. The first structure is the ground state for M=V+, and the second is the ground state for Ti and Sc-. For the lowest...... energy isomers of clusters SinM with n=14-18, we analyze the changes with size n, and impurity M of several quantities: binding energy, second difference of total energy, HOMO-LUMO gap, adiabatic electron affinity, addition energy of a Si atom, and addition energy of an M impurity to a pure Si-n cluster...

Massive M2M Access with Reliability Guarantees in LTE Systems

DEFF Research Database (Denmark)

Madueño, Germán Corrales; Kiilerich Pratas, Nuno; Stefanovic, Cedomir

2015-01-01

Machine-to-Machine (M2M) communications are one of the major drivers of the cellular network evolution towards 5G systems. One of the key challenges is on how to provide reliability guarantees to each accessing device in a situation in which there is a massive number of almost-simultaneous arriva...

Theoretical analysis of nuclear reactors (Phase I), I-V, Part III, Reactor poisoning; Razrada metoda teorijske analize nuklearnih reaktora (I faza) I-V, III Deo, Zatrovanje reaktora, I faza

Energy Technology Data Exchange (ETDEWEB)

Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1962-07-15

Method was developed for calculation of Xe{sup 135} static effect and kinetic effects of Xe{sup 135} and Sm{sup 149} with separate treatment of iodine effect and influence of reactor poisoning during power increase. Mentioned effects are treated first for uranium fuel and then the basic formulae were generalized for a mixture of fissile material. The annex contains a table with data needed for calculations and the Xe{sup 135} microscopic capture cross section dependent on temperature. Razradjen je metod proracuna statickog efekta Xe{sup 135} zatim kinetickog efekta Xe{sup 135} i Sm{sup 149} sa posebnim tretiranjem jodne jame i promene zatrovanja pri prelazu sa jedne snage na drugu. Navedeni efekti su tretirani prvo za uransko gorivo, a zatim su glavni obrasci uopsteni za smesu fisibilnih materijala. U prilogu su dati u vidu tabele, podaci potrebni za proracun i grafik zavisnosti mikroskopskog preseka zahvata Xe{sup 135} od temperature.

Theoretical analysis of nuclear reactors (Phase II), I-V, Part III, Reactor poisoning; Razrada metoda teorijske analize nuklearnih reaktora (II faza) I-V, III Deo, Zatrovanje reaktora, II faza

Energy Technology Data Exchange (ETDEWEB)

Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1962-10-15

This phase is dealing with influence of all the fission products except Xe{sup 135} on the reactivity of a reactor, usually named as reactor poisoning. The first part of the report is a review of methods for calculation of reactor poisoning. The second part shows the most frequently used method for calculation of cross sections and yields of pseudo products (for thermal neutrons). The system of equations was adopted dependent on the conditions of the available computer system. It is described in part three. Detailed method for their application is described in part four and results obtained are presented in part five.

Excitation of the high-spin isomers 180m Hf, 190m Os and 204m Pb in (γ, γ') reactions

International Nuclear Information System (INIS)

Balabanov, N.P.; Belov, A.G.; Gangrskij, Yu.P.; Kondev, F.G.; Tonchev, A.P.

1993-01-01

Excitation of isomeric states of 180 Hf (J m π = 8 - ), 190 Os (J m π = 10 - ) and 204 Pb (J m π = 9 - ) is studied for (γ, γ') reactions. The cross sections and isomeric ratios are measured using activation technique in the energy region from 6 up to 15 MeV. Experimental results were compared with statistical theory predictions. A relative contribution of different γ-ray multipolarities into the process of the population of isomeric states excited in the photoabsorption reaction and γ-cascade is investigated. (author). 32 refs.; 4 figs.; 2 tabs

Models for financial crisis detection in Indonesia based on M1, M2 per foreign exchange reverse, and M2 multiplier indicators

Science.gov (United States)

Sugiyanto; Zukhronah, Etik; Pratiwi, Esteti Sophia

2017-12-01

Indonesia has been hit by financial crisis in the middle of 1997. The financial crisis that has occurred gives a severe impact to the economy of Indonesia resulting the needs for a detection system of financial crisis. Crisis can be detected based on several indicators such as M1, M2 per foreign exchange reserves, and M2 multiplier. These three indicators can affect the exchange rate stability and may further affect the financial stability so that it can be one of the causes of the financial crisis. This research aims to determine the appropriate model that can detect the financial crisis in Indonesia. Markov switching is an alternative model that can be approach and used often for detecting financial crisis. We can determine the combination of volatility and Markov switching model with AR and volatility model are determined first. The results of this research are that M1 can be modelled by SWARCH (3, 1) while M2 per foreign research exchange reserves and M2 multiplier can be modelled by SWARCH(3,2).

Vocación médica en médicos de prestigiada conducta profesional

Directory of Open Access Journals (Sweden)

Alberto Perales

2013-10-01

Full Text Available Propósito: Estudiar la vocación médica desde una perspectiva científica. Objetivos: Analizar la vocación médica respecto a sus orígenes y factores asociados a su desarrollo en médicos considerados ejemplos de conducta profesional y vocación médica. Diseño: Investigación cualitativa, con muestreo de caso típico y entrevistas en profundidad. Institución: Instituto de Ética en Salud, Facultad de Medicina, Universidad Nacional Mayor de San Marcos, Lima, Perú. Participantes: Médicos. Metodología: La muestra estuvo conformada por 76 médicos seleccionados en base a criterios pre-establecidos, miembros de las cuatro instituciones médicas más prestigiadas del país: Academia Nacional de Medicina, Academia Peruana de Cirugía y Facultades de Medicina de la Universidad Nacional Mayor de San Marcos y Universidad Peruana Cayetano Heredia. Se obtuvo su consentimiento informado. Principales medidas de resultados: Orígenes y factores asociados a vocación médica. Resultados: El 82% correspondió al sexo masculino; edad promedio 71,6 años, con rango de edad 49 a 88 años; 8% era hijo/a de médico y 14% tenía otro familiar médico; 30% era el/la mayor de los hijos. La vocación médica no siguió un patrón único, pudiendo iniciarse en diferentes momentos del ciclo vital, incluso después de que el alumno hubo ingresado a la Facultad de Medicina. Entre los factores explicativos más frecuentemente asociados destacaron una dinámica personal y la influencia familiar, aunque hubo dos casos en los que no se encontró factor explicativo alguno. A base de los resultados se presenta definiciones de vocación y vocación médica. Conclusiones: El análisis de la información permite entender la vocación médica como un proceso que se genera en un ser humano en virtud de dos factores: uno individual y otro social (entorno que estimula su desarrollo. Su inicio puede ocurrir a edades y en formas variadas constituyéndose, finalmente, en parte del

Moment Magnitude ( M W) and Local Magnitude ( M L) Relationship for Earthquakes in Northeast India

Science.gov (United States)

Baruah, Santanu; Baruah, Saurabh; Bora, P. K.; Duarah, R.; Kalita, Aditya; Biswas, Rajib; Gogoi, N.; Kayal, J. R.

2012-11-01

An attempt has been made to examine an empirical relationship between moment magnitude ( M W) and local magnitude ( M L) for the earthquakes in the northeast Indian region. Some 364 earthquakes that were recorded during 1950-2009 are used in this study. Focal mechanism solutions of these earthquakes include 189 Harvard-CMT solutions ( M W ≥ 4.0) for the period 1976-2009, 61 published solutions and 114 solutions obtained for the local earthquakes (2.0 ≤ M L ≤ 5.0) recorded by a 27-station permanent broadband network during 2001-2009 in the region. The M W- M L relationships in seven selected zones of the region are determined by linear regression analysis. A significant variation in the M W- M L relationship and its zone specific dependence are reported here. It is found that M W is equivalent to M L with an average uncertainty of about 0.13 magnitude units. A single relationship is, however, not adequate to scale the entire northeast Indian region because of heterogeneous geologic and geotectonic environments where earthquakes occur due to collisions, subduction and complex intra-plate tectonics.

M N Deshpande

Indian Academy of Sciences (India)

Articles written in Resonance – Journal of Science Education. Volume 7 Issue 7 July 2002 pp 89-91 Think It Over. A Problem in Number Theory · M N Deshpande · More Details Fulltext PDF. Volume 7 Issue 7 July 2002 pp 91-91 Think It Over. A Geometric Dissection Problem · M N Deshpande · More Details Fulltext PDF.

V M Gurame

Indian Academy of Sciences (India)

Home; Journals; Bulletin of Materials Science. V M Gurame. Articles written in Bulletin of Materials Science. Volume 38 Issue 2 April 2015 pp 483-491. Spray deposited CeO2–TiO2 counter electrode for electrochromic devices · A K Bhosale S R Kulal V M Gurame P S Patil · More Details Abstract Fulltext PDF. Optically ...

Self-mídia

DEFF Research Database (Denmark)

Fausing, Bent

2015-01-01

O self e a identidade não são apenas tópicos relacionados aos selfies. Eles estão ligados ao desenvolvimento das mídias desde o Renascimento, as self-mídias. Esta é a tese a seguir. O sujeito, o self, é mais claramente exposto no rosto; e rosto e identidade tornam-se importantes nas mídias desde o...

THE NEXT GENERATION VIRGO CLUSTER SURVEY. X. PROPERTIES OF ULTRA-COMPACT DWARFS IN THE M87, M49, AND M60 REGIONS

Energy Technology Data Exchange (ETDEWEB)

Liu, Chengze [Center for Astronomy and Astrophysics, Department of Physics and Astronomy, Shanghai Jiao Tong University, Shanghai 200240 (China); Peng, Eric W.; Zhang, Hong-Xin [Department of Astronomy, Peking University, Beijing 100871 (China); Côté, Patrick; Ferrarese, Laura; Gwyn, Stephen; Blakeslee, John P. [Herzberg Institute of Astrophysics, National Research Council of Canada, Victoria, BC V9E 2E7 (Canada); Jordán, Andrés; Muñoz, Roberto P.; Puzia, Thomas H. [Instituto de Astrofísica, Facultad de Física, Pontificia Universidad Católica de Chile, Av. Vicuña Mackenna 4860, 7820436 Macul, Santiago (Chile); Mihos, J. Christopher [Department of Astronomy, Case Western Reserve University, Cleveland, OH (United States); Lançon, Ariane [Observatoire Astronomique de Strasbourg, Université de Strasbourg and CNRS, UMR 7550, 11 rue de l’Université, F-67000 Strasbourg (France); Cuillandre, Jean-Charles [CEA/IRFU/SAp, Laboratoire AIM Paris-Saclay, CNRS/INSU, Université Paris Diderot, Observatoire de Paris, PSL Research University, F-91191 Gif-sur-Yvette Cedex (France); Boselli, Alessandro [Aix-Marseille Université, CNRS, LAM (Laboratoire d’Astrophysique de Marseille) UMR 7326, F-13388, Marseille (France); Durrell, Patrick R., E-mail: czliu@sjtu.edu.cn, E-mail: peng@pku.edu.cn [Department of Physics and Astronomy, Youngstown State University, One University Plaza, Youngstown, OH 44555 (United States); and others

2015-10-10

We use imaging from the Next Generation Virgo cluster Survey (NGVS) to present a comparative study of ultra-compact dwarf (UCD) galaxies associated with three prominent Virgo sub-clusters: those centered on the massive red-sequence galaxies M87, M49, and M60. We show how UCDs can be selected with high completeness using a combination of half-light radius and location in color–color diagrams (u*iK{sub s} or u*gz). Although the central galaxies in each of these sub-clusters have nearly identical luminosities and stellar masses, we find large differences in the sizes of their UCD populations, with M87 containing ∼3.5 and 7.8 times more UCDs than M49 and M60, respectively. The relative abundance of UCDs in the three regions scales in proportion to sub-cluster mass, as traced by X-ray gas mass, total gravitating mass, number of globular clusters (GCs), and number of nearby galaxies. We find that the UCDs are predominantly blue in color, with ∼85% of the UCDs having colors similar to blue GCs and stellar nuclei of dwarf galaxies. We present evidence that UCDs surrounding M87 and M49 may follow a morphological sequence ordered by the prominence of their outer, low surface brightness envelope, ultimately merging with the sequence of nucleated low-mass galaxies, and that envelope prominence correlates with distance from either galaxy. Our analysis provides evidence that tidal stripping of nucleated galaxies is an important process in the formation of UCDs.

STS-107 M.S. Laurel Clark during TCDT M113 training activities

Science.gov (United States)

2002-01-01

KENNEDY SPACE CENTER, FLA. -- STS-107 Mission Specialist Laurel Clark (in yellow cap) is instructed on the operation of an M113 armored personnel carrier during Terminal Countdown Demonstration Test activities, a standard part of launch preparations. STS-107 is a mission devoted to research and will include more than 80 experiments that will study Earth and space science, advanced technology development, and astronaut health and safety. Launch is planned for Jan. 16, 2003, between 10 a.m. and 2 p.m. EST aboard Space Shuttle Columbia.

mRNA processing in yeast

International Nuclear Information System (INIS)

Stevens, A.

1982-01-01

Investigations in this laboratory center on basic enzymatic reactions of RNA. Still undefined are reactions involved in the conversion of precursors of mRA (pre-mRNA) to mRNA in eukaryotes. The pre-mRNA is called heterogeneous nuclear RNA and is 2 to 6 times larger than mRNA. The conversion, called splicing, involves a removal of internal sequences called introns by endoribonuclease action followed by a rejoining of the 3'- and 5'-end fragments, called exons, by ligating activity. It has not been possible yet to study the enzymes involved in vitro. Also undefined are reactions involved in the turnover or discarding of certain of the pre-mRNA molecules. Yeast is a simple eukaryote and may be expected to have the same, but perhaps simpler, processing reactions as the higher eukaryotes. Two enzymes involved in the processing of pre-mRNA and mRNA in yeast are under investigation. Both enzymes have been partially purified from ribonucleoprotein particles of yeast. The first is a unique decapping enzyme which cleaves [ 3 H]m 7 Gppp [ 14 C]RNA-poly (A) of yeast, yielding [ 3 H]m 7 GDP and is suggested by the finding that the diphosphate product, m 7 GpppA(G), and UDP-glucose are not hydrolyzed. The second enzyme is an endoribonuclease which converts both the [ 3 H] and [ 14 C] labels of [ 3 H]m 7 Gppp[ 14 C]RNA-poly(A) from an oligo(dT)-cellulose bound form to an unbound, acid-insoluble form. Results show that the stimulation involves an interaction of the labeled RNA with the small nuclear RNA. The inhibition of the enzyme by ethidium bromide and its stimulation by small nuclear RNA suggest that it may be a processing ribonuclease, requiring specific double-stranded features in its substrate. The characterization of the unique decapping enzyme and endoribonuclease may help to understand reactions involved in the processing of pre-mRNA and mRNA in eukaryotes

sup(99)Tcsup(m)-ascorbate

International Nuclear Information System (INIS)

Persson, R.B.R.; Strand, S.E.; White, T.

1975-01-01

The sup(99)Tcsup(m)-ascorbate preparation used in this investigation contained FeCl 3 4mN, asorbic acid 110 mM and had an initial pH-value of 7.4 and a final pH-value of 6.8. Studies of the complex-formation were performed with gel-chromatography column-scanning (GCS), which is the analytical method to be preferred for this type of compound, indicated that the complex was formed in two steps. First reduced hydrolyzed sup(99)Tcsup(m) was formed rapidly and the sup(99)Tcsup(m)-ascorbate was formed by a slower reaction (k = 3, 10 -2 min -1 ). The renal uptake of sup(99)Tcsup(m)- was studied in 29 patients with a gamma-camera. The time-course of radio-activity in kidneys, 'tissue background'-areas and in blood suggested that optimal conditions for kidney-imaging were reached 3 to 6 hr after injection. About 20% of the sup(99)Tcsup(m)-ascorbate was bound to plasma-proteins, and only a small fraction to red blood-cells. The disappearance of the sup(99)Tcsup(m)-ascorbate from plasma followed a three-exponential curve: 40% with a half-life of 0.2 hr, 30% with a half-life of 20 hr. The absorbed radiation dose to the kidneys was about 200 (SE +- 60) mrad mCi -1 and to the whole-body 10 (SE +- 3) mrad mCi -1 of administered activity. There was a close correlation (r + 0.98) of the separate renal uptake (dx:(dx +sin)) of sup(99)Tcsup(m)-ascorbate to the separate renal function as determined with 131 I-Hippuran. (author)

ANTESEDEN ATTITUDE TOWARDS M-BANKING DAN DAMPAKNYA TERHADAP BEHAVIORAL INTENTION TO ADOPT M-BANKING

Directory of Open Access Journals (Sweden)

Titon Adrinanto

2016-02-01

Full Text Available The background of this research was m­banking users in Indonesia is still low despite the mobile phone users in developed and developing countries in the world has increased rapidly since 21st century. Some bank companies in Indonesia has been offering m­banking service but the use of m­banking for financial transaction is still low and limited. The objectives of this research was to analyze the antecedents of attitude towards m­banking and its impact on behavioral intention to adopt m­banking. The design of this research applies hypothesis testing. 200 samples selected from prospective user of 3 government bank. The sampling technique was purposive sampling with cross­sectional study. Data analysis used in this research was collected by questionnaire technique with item of statements for each variable. In order to obtain valid and reliable instrument tool, validity and reliability test has been done. The result of this research conclude that there is positive effect perceived usefulness, perceived ease of use, perceived competence, perceived communication, perceived privacy and security, society influence, and facilitating condition on attitude towards m­banking. This study supports that there is positive influence on attitude towards m­banking on behavioral intention to adopt m­banking.

Comparison of Rubazyme-M and MACRIA for the detection of rubella-specific IgM

Energy Technology Data Exchange (ETDEWEB)

Best, J.M.; Palmer, S.J.; Morgan-Capner, P.; Hodgson, J. (Saint Thomas' Hospital, London (UK))

1984-02-01

One hundred and eighty-six carefully selected sera were tested for rubella-specific IgM by Rubazyme-M (Abbott Diagnostics) and an M-antibody capture radioimmunoassay (MACRIA). Eleven of these sera were from cases of infectious mononucleosis, six of which gave positive results in MACRIA, while one gave a positive result in Rubazyme-M. Of the remaining 175 sera, 158 gave concordant results whilst 17 sera gave discordant results; these 17 were also tested by serum fractionation. Problems were encountered with all assay systems used. It is therefore recommended that the results of all tests for rubella-specific IgM should be interpreted with caution.

Requisitos globales mínimos esenciales en educación médica

Directory of Open Access Journals (Sweden)

Full Text Available El proceso de la globalización, cada día más evidente en la educación médica, ha convertido en asunto urgente la tarea de definir las capacidades esenciales que requieren los "médicos globalizados". De este asunto se ha ocupado el recientemente creado Instituto para la Educación Médica Internacional, IEMI (Institute for International Medical Education IIME. El Comité Central del IEMI desarrolló el concepto de "requisitos globales mínimos esenciales" (RGME y definió un conjunto de resultados mínimos del aprendizaje, aplicables en todo el mundo, que los estudiantes de las escuelas (facultades de medicina deben demostrar para poder obtener su grado. Estos "requisitos esenciales" se agrupan en siete grandes categorías educacionales y comprenden 60 objetivos de aprendizaje. Además de estas "capacidades globales", las escuelas de medicina deben agregar requisitos nacionales y locales. El enfocar las capacidades de los estudiantes como resultados de la educación médica debe tener implicaciones profundas en el contenido curricular y en los procesos educacionales de las escuelas (facultades de medicina.

Requisitos globales mínimos esenciales en educación médica

Directory of Open Access Journals (Sweden)

2003-09-01

Full Text Available El proceso de la globalización, cada día más evidente en la educación médica, ha convertido en asunto urgente la tarea de definir las capacidades esenciales que requieren los "médicos globalizados". De este asunto se ha ocupado el recientemente creado Instituto para la Educación Médica Internacional, IEMI (Institute for International Medical Education IIME. El Comité Central del IEMI desarrolló el concepto de "requisitos globales mínimos esenciales" (RGME y definió un conjunto de resultados mínimos del aprendizaje, aplicables en todo el mundo, que los estudiantes de las escuelas (facultades de medicina deben demostrar para poder obtener su grado. Estos "requisitos esenciales" se agrupan en siete grandes categorías educacionales y comprenden 60 objetivos de aprendizaje. Además de estas "capacidades globales", las escuelas de medicina deben agregar requisitos nacionales y locales. El enfocar las capacidades de los estudiantes como resultados de la educación médica debe tener implicaciones profundas en el contenido curricular y en los procesos educacionales de las escuelas (facultades de medicina.

Jaan Ruus soovitab : "Parfüüm : ühe mõrva lugu" / Jaan Ruus

Index Scriptorium Estoniae

Ruus, Jaan, 1938-2017

2006-01-01

Patrick Süskindi krimiromaani "Parfüüm" ekraniseering "Parfüüm : ühe mõrva lugu" ("Perfume: The Story of a Murderer") : režissöör Tom Tykwer : peaosas Ben Whishaw : Ameerika Ühendriigid - Saksamaa 2006

UltramicroELISA para la detección de anticuerpos IgM anti M. leprae UltramicroELISA assay for the detection of human IgM antibodies to M. leprae

Directory of Open Access Journals (Sweden)

José Laferte

1991-12-01

Full Text Available La disponibilidad del sistema Ultramicroanalítico (SUMA y de un antígeno especie-específico del M. leprae obtenido mediante síntesis química, permitió la normalización y validación de un ultramicroELISA para la detección de anticuerpos IgM específicos a esta micobacteria. El análisis de 433 sueros de banco de sangre y 265 sueros usados para validar el método y clasificados en un grupo control de donantes de banco de sangre (100, un grupo de pacientes tuberculosos (50, un grupo de enfermos de lepra (65 y un grupo de contactos de estos enfermos (50, mostró la especificidad del ensayo para evidenciar la infección con el M. leprae. Los resultados obtenidos del estudio adicional de 140 muestras de suero de contactos de enfermos estuvieron estrechamente correlacionados (r = 0,98 con los resultados obtenidos por la técnica de microELISA convencional. La utilización del SUMA no solo permite un notable ahorro de reactivos si no además facilita la lectura, cálculo, validación y almacenamiento automático de los resultados.The availability of an ultramicroanalitic system (SUMA and specie-specific antigen of M. leprae obtained by chemical synthesis, have made possible the standardization and validation of an ultramicroELISA assay for detecting specific human IgM antibodies to this mycobacterium. The specificity of this test to demonstrate the infection with M. leprae was corroborated through a screening of 433 blood bank serum samples and other 265 from diferent groups (100, control group, 50 tuberculosis patients, 65 leprosy patients, 50 from household. The results obtained in the aditional study of 140 household sero showed a high correlation (r = 0.98 with the conventional microELISA method. The use of SUMA allows saving reagents and time since sample handling, plate reading, print out and storing the data are computer assisted.

Supersymmetric states in M5/M2 CFTs

International Nuclear Information System (INIS)

Bhattacharyya, Sayantani; Minwalla, Shiraz

2007-01-01

We propose an exact, finite N formula for the partition function over 1/4 th BPS states in the conformal field theory on the world volume of N coincident M5 branes, and 1/8 th BPS states in the theory of N conincident M2 branes. We obtain our partition function by performing the radial quantization of the Coulomb Branches of these theories and rederive the same formula from the quantization of supersymmetric giant and dual giant gravitons in AdS 7 x S 4 and AdS 4 x S 7 . Our partition function is qualitatively similar to the analogous quantity in N = 4 Yang Mills. It reduces to the sum over supersymmetric multi gravitons at low energies, but deviates from this supergravity formula at energies that scale like a positive power of N

Hyperglycemia induces mixed M1/M2 cytokine profile in primary human monocyte-derived macrophages.

Science.gov (United States)

Moganti, Kondaiah; Li, Feng; Schmuttermaier, Christina; Riemann, Sarah; Klüter, Harald; Gratchev, Alexei; Harmsen, Martin C; Kzhyshkowska, Julia

2017-10-01

Hyperglycaemia is a key factor in diabetic pathology. Macrophages are essential regulators of inflammation which can be classified into two major vectors of polarisation: classically activated macrophages (M1) and alternatively activated macrophages (M2). Both types of macrophages play a role in diabetes, where M1 and M2-produced cytokines can have detrimental effects in development of diabetes-associated inflammation and diabetic vascular complications. However, the effect of hyperglycaemia on differentiation and programming of primary human macrophages was not systematically studied. We established a unique model to assess the influence of hyperglycaemia on M1 and M2 differentiation based on primary human monocyte-derived macrophages. The effects of hyperglycaemia on the gene expression and secretion of prototype M1 cytokines TNF-alpha and IL-1beta, and prototype M2 cytokines IL-1Ra and CCL18 were quantified by RT-PCR and ELISA. Hyperglycaemia stimulated production of TNF-alpha, IL-1beta and IL-1Ra during macrophage differentiation. The effect of hyperglycaemia on TNF-alpha was acute, while the stimulating effect on IL-1beta and IL-1Ra was constitutive. Expression of CCL18 was supressed in M2 macrophages by hyperglycaemia. However the secreted levels remained to be biologically significant. Our data indicate that hyperglycaemia itself, without additional metabolic factors induces mixed M1/M2 cytokine profile that can support of diabetes-associated inflammation and development of vascular complications. Copyright © 2016 Elsevier GmbH. All rights reserved.

The M2 Channel

DEFF Research Database (Denmark)

Santner, Paul

Drug resistance of Influenza A against antivirals is an increasing problem. No effective Influenza A drugs targeting the crucial viral protein, the proton transporter M2 are available anymore due to widespread resistance. Thanks to research efforts elucidating M2 protein structure, function and i...... resistance escape routes from drug inhibition. We thereby were hopefully able to provide a platform for the large-scale evaluation of M2 channel activity, inhibitors and resistance....

Kontsertetendused Eesti mõisates

Index Scriptorium Estoniae

2008-01-01

15.-24. augustini toimub kuues Eesti mõisas kontsertetenduste sari "Eesti mõisad 2008", kus esinevad barokkansambel Corelli Consort ja Fine 5 Tantsuteater. Mõisate ajalugu tutvustab Jüri Kuuskemaa

Logistika mõisted

Index Scriptorium Estoniae

2003-01-01

Järg 18. märts lk. 19, 29. aprill lk. 17, 20. mai lk. 14, 19. august lk. 24, 23. september lk. 12, 4. november, 2. dets. lk. 16, 20. jaanuar 2004 lk. 10, 2. märts lk. 20, 6. aprill lk. 22, 4. mai lk. 16, 1. juuni lk. 14, 5. juuli, 2. august lk. 18, 5. oktoober lk. 22, 7. dets. lk. 23. Logistika põhimõisted

IBM model M keyboard

CERN Multimedia

1985-01-01

In 1985, the IBM Model M keyboard was created. This timeless classic was a hit. IBM came out with several varients of the model M. They had the space saver 104 key which is the one most seen today and many international versions of that as well. The second type, and rarest is the 122 key model M which has 24 extra keys at the very top, dubbed the “programmers keyboard”. IBM manufactured these keyboards until 1991. The model M features “caps” over the actual keys that can be taken off separately one at a time for cleaning or to replace them with colored keys or keys of another language, that was a very cost effective way of shipping out internationally the keyboards.

A dynamic network model of mTOR signaling reveals TSC-independent mTORC2 regulation

NARCIS (Netherlands)

Dalle Pezze, Piero; Sonntag, Annika G; Thien, Antje; Prentzell, Mirja T; Gödel, Markus; Fischer, Sven; Neumann-Haefelin, Elke; Huber, Tobias B; Baumeister, Ralf; Shanley, Daryl P; Thedieck, Kathrin

2012-01-01

The kinase mammalian target of rapamycin (mTOR) exists in two multiprotein complexes (mTORC1 and mTORC2) and is a central regulator of growth and metabolism. Insulin activation of mTORC1, mediated by phosphoinositide 3-kinase (PI3K), Akt, and the inhibitory tuberous sclerosis complex 1/2

Muzeum módy - Tokyo 2010

OpenAIRE

Kráľová, Zuzana

2010-01-01

navrhovaný objekt je múzeum módy pre mesto Tokio. Múzeum sa bude nachádzať na pulzujúcej tepne tokijského módneho diania. Navrhovaná budova presahuje 100m výšky a jej zbierky mapujú vývoj svetovej módy 20.storčia. Taktiež je dejiskom konania živých módnych show a priestorom pre prezentáciu tvorby mladých módnych tvorcov. Samotné artefakty zbierky sú vystavované jednotným systémom - zavesením. visiace figuríny prechádzajú kontinuálne celým výstavným priestorom, návštevníkovi je umožnený pohyb ...

Rac2 controls tumor growth, metastasis and M1-M2 macrophage differentiation in vivo.

Directory of Open Access Journals (Sweden)

Shweta Joshi

Full Text Available Although it is well-established that the macrophage M1 to M2 transition plays a role in tumor progression, the molecular basis for this process remains incompletely understood. Herein, we demonstrate that the small GTPase, Rac2 controls macrophage M1 to M2 differentiation and the metastatic phenotype in vivo. Using a genetic approach, combined with syngeneic and orthotopic tumor models we demonstrate that Rac2-/- mice display a marked defect in tumor growth, angiogenesis and metastasis. Microarray, RT-PCR and metabolomic analysis on bone marrow derived macrophages isolated from the Rac2-/- mice identify an important role for Rac2 in M2 macrophage differentiation. Furthermore, we define a novel molecular mechanism by which signals transmitted from the extracellular matrix via the α4β1 integrin and MCSF receptor lead to the activation of Rac2 and potentially regulate macrophage M2 differentiation. Collectively, our findings demonstrate a macrophage autonomous process by which the Rac2 GTPase is activated downstream of the α4β1 integrin and the MCSF receptor to control tumor growth, metastasis and macrophage differentiation into the M2 phenotype. Finally, using gene expression and metabolomic data from our Rac2-/- model, and information related to M1-M2 macrophage differentiation curated from the literature we executed a systems biologic analysis of hierarchical protein-protein interaction networks in an effort to develop an iterative interactome map which will predict additional mechanisms by which Rac2 may coordinately control macrophage M1 to M2 differentiation and metastasis.

A 18 m 2 cylindrical tracking detector made of 2.6 m long, stereo mylar straw tubes with 100 μm resolution

Science.gov (United States)

Benussi, L.; Bertani, M.; Bianco, S.; Fabbri, F. L.; Gianotti, P.; Giardoni, M.; Ghezzo, A.; Guaraldo, C.; Lanaro, A.; Locchi, P.; Lu, J.; Lucherini, V.; Mecozzi, A.; Pace, E.; Passamonti, L.; Qaisar, N.; Ricciardi, A.; Sarwar, S.; Serdyouk, V.; Trasatti, L.; Volkov, A.; Zia, A.

1998-12-01

An array of 2424 2.6 m-long, 15 mm-diameter mylar straw tubes, arranged in two axial and four stereo layers, has been assembled. The array covers a cylindrical tracking surface of 18 m 2 and provides coordinate measurement in the drift direction and along the wire. A correction of the systematic effects which are introduced by gravitational sag and electrostatics, thus dominating the detector performance especially with long straws, allows to determine wire position from drift-time distribution. The correction has been applied to reach a space resolution of 40 μm with DME, 100 μm with Ar+C 2H 6, and 100-200 μm with CO 2. Such a resolution is the best ever obtained for straws of these dimensions. A study of the gas leakage for the straw system has been performed, and results are reported. The array is being commissioned as a subdetector of the FINUDA spectrometer, and tracking performances are being studied with cosmic rays.

A 18 m2 cylindrical tracking detector made of 2,6 m long, stereo mylar straw tubes with 100 μm resolution

International Nuclear Information System (INIS)

Benussi, L.; Bertani, M.; Bianco, S.; Fabbri, F.L.; Gianotti, P.; Giardoni, M.; Ghezzo, A.; Guaraldo, C.; Lanaro, A.; Locchi, P.; Lu, J.; Lucherini, V.; Mecozzi, A.; Pace, E.; Passamonti, L.; Qaisar, N.; Ricciardi, A.; Sarwar, S.; Serdyouk, V.; Trasatti, L.; Volkov, A.; Zia, A.

1998-01-01

An array of 2424 2.6 m-long, 15 mm-diameter mylar straw tubes, arranged in two axial and four stereo layers, has been assembled. The array covers a cylindrical tracking surface of 18 m 2 and provides coordinate measurement in the drift direction and along the wire. An under-standing of the systematic effects which are introduced by gravitational sag and electrostatics, thus dominating the detector performance especially with long straws, allows to determine wire position from drift-time distribution. The correction has been applied to reach a space resolution of 40 μm with DME, 100 μm with Ar + C 2 H 6 , and 100-200 μm with CO 2 . Such a resolution is the best ever obtained for straws of these dimensions. A study of the gas leakage for the straw system has been performed, and results are reported. The array is being commissioned as a subdetector of the FINUDA spectrometer, and tracking performances are being studied with cosmic rays. (author)

RESTful M2M Gateway for Remote Wireless Monitoring for District Central Heating Networks

Directory of Open Access Journals (Sweden)

Bo Cheng

2014-11-01

Full Text Available In recent years, the increased interest in energy conservation and environmental protection, combined with the development of modern communication and computer technology, has resulted in the replacement of distributed heating by central heating in urban areas. This paper proposes a Representational State Transfer (REST Machine-to-Machine (M2M gateway for wireless remote monitoring for a district central heating network. In particular, we focus on the resource-oriented RESTful M2M gateway architecture, and present an uniform devices abstraction approach based on Open Service Gateway Initiative (OSGi technology, and implement the resource mapping mechanism between resource address mapping mechanism between RESTful resources and the physical sensor devices, and present the buffer queue combined with polling method to implement the data scheduling and Quality of Service (QoS guarantee, and also give the RESTful M2M gateway open service Application Programming Interface (API set. The performance has been measured and analyzed. Finally, the conclusions and future work are presented.

IRF models associated with representations of the Lie superalgebras gl(m|n) and sl(m|n)

International Nuclear Information System (INIS)

Deguchi, T.; Fujii, A.

1991-01-01

This paper presents two families of exactly solvable interaction round a face (IRF) models associated with representations of the Lie superalgebras gl(m/n) and sl(m/n). These IRF models are the generalizations of integrable spin chains with bosons and fermions. The authors present fusion models associated with higher representations of gl(m/n) and sl(m/n). The authors introduce restricted IRF models both for gl(m/n) and sl(m/n)

BFCA for labeling with the M(CO)3 precursor (M = Re, 99mTc) : cysteine toward a tridentate complex

International Nuclear Information System (INIS)

Hong, Young Don; Choi, Ok Ja; Gwon, Hui Jeong; Choi, Sang Mu; Park, Sang Hyun; Park, Kyung Bae; Choi, Sun Ju

2004-01-01

Organometallic complexes of techneutium in its low oxidation states received little attention till the development of very stable water-soluble organometallic Tc(I) complexes using monodentate isonitrile ligands. The Tc(I) oxidation state is pratically advantegeous because of the kinetic inertness inherent in its low-spin d 6 configuration and good stability in aqueous media. That is, Tc(I) or Re(I) tricarbonyl complexes are ideal candidates for the radiolabeling of biomolecules which M(CO) 3 core allows the high efficient labelling with the retention of the biological affinity. To be used as a BFCA, it should possess not only both a strong metal-binding moiety and a group that binds to a biomolecules, but also the metal complex should maintain the high stability in vitro and in vivo. In this investigation, to estimate the usefulness of thiol modified L-cysteine as a new BFCA with M(CO)3 precursor for the conjugation to biomolecules while maintaining high stability, their non-carrier added and macroscopic level complexes of L-cycteine (L 1 ), S-methyl L-cysteine (L 2 ), L-methionine (L 3 ), and S-carboxymethyl-L-cysteine (L 4 ) were prepared for the evaluation of radiolabelling efficiency with 99m Tc(CO) 3 and macroscopic characteristics. Furthermore, in order to study in vivo pharmacokinetics, scintigraphic imaging scans using gamma camera were acquired after intravenous administration of each 99m Tc(CO) 3 complex and biodistribution study on 99m Tc(CO) 3 -L 4 was implemented using ICR mice

Thermoelectric Performance of the MXenes M2CO2 (M = Ti, Zr, or Hf)

KAUST Repository

Gandi, Appala; Alshareef, Husam N.; Schwingenschlö gl, Udo

2016-01-01

MXenes, M2CO2, where M = Ti, Zr, or Hf, in order to evaluate the effect of the metal M on the thermoelectric performance. The lattice contribution to the thermal conductivity, obtained from the phonon life times, is found to be lowest in Ti2CO2

m6AVar: a database of functional variants involved in m6A modification

OpenAIRE

Zheng, Yueyuan; Nie, Peng; Peng, Di; He, Zhihao; Liu, Mengni; Xie, Yubin; Miao, Yanyan; Zuo, Zhixiang; Ren, Jian

2017-01-01

Abstract Identifying disease-causing variants among a large number of single nucleotide variants (SNVs) is still a major challenge. Recently, N 6-methyladenosine (m6A) has become a research hotspot because of its critical roles in many fundamental biological processes and a variety of diseases. Therefore, it is important to evaluate the effect of variants on m6A modification, in order to gain a better understanding of them. Here, we report m6AVar (http://m6avar.renlab.org), a comprehensive da...

99mTc-Tetrofosmin scintimammography in suspected breast cancer patients: comparison with 99mTc-MIBI

International Nuclear Information System (INIS)

Kim, Seong Jang; Kim, In Ju; Kim, Yong Ki; Bae, Young Tae

2000-01-01

The aim of this study was to investigate the diagnostic role of 99m Tc-Tetrofosmin in detection of breast cancer and compared with that of 99m Tc-MIBI. Forty-eight patients with a clinically palpable mass or abnormal mammographic or ultrasonographic findings had 99m Tc-MIBI and 99m Tc-Tetrofosmin scintimammographies after intravenous injection of 925 MBq of radiopharmaceuticals. The scintimammographs were correlated with histopathologic findings. Thirty-three patients were diagnosed with breast cancer and 15 patients with benign breast diseases. The numbers of true positive, true negative, false positive, and false negative cases of 99m Tc-MIBI scintimammography were 29, 10, 5, and 4 respectively. The sensitivity, specificity, positive predictive value, and negative predictive value of 99m Tc-MIBI scintimammographies were 87.8%, 66.7%, 85.3%, and 71.4% respectively. The numbers of true positive, true negative, false positive, and false negative cases of 99m Tc-Tetrofosmin were 31, 10, 5, and 2 respectively. The sensitivity, specificity, positive predictive value, negative predictive value of 99m Tc-Tetrofosmin were 93.9%, 66.7%, 86.1%, and 73.3% respectively. One patient was false negative in both 99m Tc-Tetrofosmin scintimammographies and its size was 0.5cm. 99m Tc-Tetrofosmin and 99m Tc-MIBI were non-invasive and useful in detection of breast cancer and 99m Tc-Tetrofosmin was comparable to the 99m Tc-MIBI in detection of primary breast cancer.=20

Synthesis of 99mTc-oxybutynin for M3-receptor-mediated imaging of urinary bladder

International Nuclear Information System (INIS)

Moustapha, M.E.; Benha University, Benha; Motaleb, M.A.; Ibrahim, I.T.

2011-01-01

Radiolabeling of oxybutynin, a muscarinic acetylcholine (mACh) receptor antagonist agent with 99m Tc is of considerable interest for imaging of urinary bladder. This study is aimed to optimize radiolabeling yield of oxybutynin with 99m Tc using SnCl 2 x 2H 2 O as a reducing agent with respect to factors that affect the reaction conditions such as oxybutynin amount, stannous chloride amount, reaction time and pH of the reaction mixture. In vitro stability of the radiolabeled complex was checked and it was found to be stable for up to 8 h. 99m Tc-oxybutynin was injected via subcutaneous and intravenous administration routes into normal Sprague-Dawley rats. Biodistribution studies have revealed that 99m Tc-oxybutynin exhibits high affinity and specificity for the muscarinic M 3 subtype located on the smooth muscle of urinary bladder relative to the M 1 and M 2 subtypes of the G protein coupled receptor (GPCR) superfamily. In vivo uptake of subcutaneous 99m Tc-oxybutynin in urinary bladder was 19.6 ± 0.42% ID at 0.5 h, whereas in intravenous administration route the accumulation in the urinary bladder was found to be 9.4 ± 0.31% ID at 0.5 h post injection. Administration of cold oxybutynin effectively blocked urinary bladder uptake and further confirms the high specificity of this complex for the M 3 receptor. (author)

Presynaptic mGlu1 and mGlu5 autoreceptors facilitate glutamate exocytosis from mouse cortical nerve endings.

Science.gov (United States)

Musante, Veronica; Neri, Elisa; Feligioni, Marco; Puliti, Aldamaria; Pedrazzi, Marco; Conti, Valerio; Usai, Cesare; Diaspro, Alberto; Ravazzolo, Roberto; Henley, Jeremy M; Battaglia, Giuseppe; Pittaluga, Anna

2008-09-01

The effects of mGlu1 and mGlu5 receptor activation on the depolarization-evoked release of [3H]d-aspartate ([3H]D-ASP) from mouse cortical synaptosomes were investigated. The mGlu1/5 receptor agonist 3,5-DHPG (0.1-100microM) potentiated the K+(12mM)-evoked [3H]D-ASP overflow. The potentiation occurred in a concentration-dependent manner showing a biphasic pattern. The agonist potentiated [3H]D-ASP exocytosis when applied at 0.3microM; the efficacy of 3,5-DHPG then rapidly declined and reappeared at 30-100microM. The fall of efficacy of agonist at intermediate concentration may be consistent with 3,5-DHPG-induced receptor desensitization. Facilitation of [3H]D-ASP exocytosis caused by 0.3microM 3,5-DHPG was prevented by the selective mGlu5 receptor antagonist MPEP, but was insensitive to the selective mGlu1 receptor antagonist CPCCOEt. In contrast, CPCCOEt prevented the potentiation by 50microM 3,5-DHPG, while MPEP had minimal effect. Unexpectedly, LY 367385 antagonized both the 3,5-DHPG-induced effects. A total of 0.3microM 3,5-DHPG failed to facilitate the K+-evoked [3H]D-ASP overflow from mGlu5 receptor knockout (mGlu5-/-) cortical synaptosomes, but not from nerve terminals prepared from the cortex of animals lacking the mGlu1 receptors, the crv4/crv4 mice. On the contrary, 50microM 3,5-DHPG failed to affect the [3H]D-ASP exocytosis from cortical synaptosomes obtained from crv4/crv4 and mGlu5-/-mice. Western blot analyses in subsynaptic fractions support the existence of both mGlu1 and mGlu5 autoreceptors located presynaptically, while immunocytochemistry revealed their presence at glutamatergic terminals. We propose that mGlu1 and mGlu5 autoreceptors exist on mouse glutamatergic cortical terminals; mGlu5 receptors may represent the "high affinity" binding sites for 3,5-DHPG, while mGlu1 autoreceptors represent the "low affinity" binding sites.

Pulsations in M dwarf stars

OpenAIRE

Rodríguez-López, C.; MacDonald, J.; Moya, A.

2011-01-01

We present the results of the first theoretical non-radial non-adiabatic pulsational study of M dwarf stellar models with masses in the range 0.1 to 0.5M_solar. We find the fundamental radial mode to be unstable due to an \\epsilon mechanism caused by deuterium (D-) burning for the young 0.1 and 0.2M_solar models, by non-equilibrium He^3 burning for the 0.2 and 0.25M_solar models of 10^4Myr, and by a flux blocking mechanism for the partially convective 0.4 and 0.5M_solar models once they reach...

Technical aspects regarding the management of radioactive waste from decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Dragolici, F.; Turcanu, C.N.; Rotarescu, Gh.; Paunica, I.

2002-01-01

The proper application of the nuclear techniques and technologies in Romania started in 1957 with the commissioning of the VVR-S Research Reactor at IFIN-HH-Magurele. During the past 40 years, this reactor was used for thousands of nuclear applications with extremely diverse profiles (research, biology, medicine, education, agriculture, transport, all types of industry) which used radioactive sources in their activity and produced radioactive waste. The Radioactive Waste Treatment Plant (STDR) at IFIN-HH was constructed in collaboration with companies from the United Kingdom and became operational in 1975. It was the only authorized and specialized institution for the management of non-fuel cycle radioactive waste in Romania. Using the concepts existing in the 1980's concerning the final disposal of the low and intermediate level radioactive wastes, and applying internal standards and international recommendations, the National Repository for Low and Intermediate Radioactive Waste (DNDR) was built in 1985 in Baita, Bihor county and placed into operation. Therefore, through the construction and operation of the treatment and final disposal capabilities, Romania has solved the management of the low and intermediate level radioactive waste while providing for the protection of the people and environment. (author)

Rac1 Regulates the Activity of mTORC1 and mTORC2 and Controls Cellular Size

Science.gov (United States)

Saci, Abdelhafid; Cantley, Lewis C.; Carpenter, Christopher L.

2013-01-01

SUMMARY Mammalian target of rapamycin (mTOR) is a serine/threonine kinase that exists in two separate complexes, mTORC1 and mTORC2, that function to control cell size and growth in response to growth factors, nutrients, and cellular energy levels. Low molecular weight GTP-binding proteins of the Rheb and Rag families are key regulators of the mTORC1 complex, but regulation of mTORC2 is poorly understood. Here, we report that Rac1, a member of the Rho family of GTPases, is a critical regulator of both mTORC1 and mTORC2 in response to growth-factor stimulation. Deletion of Rac1 in primary cells using an inducible-Cre/Lox approach inhibits basal and growth-factor activation of both mTORC1 and mTORC2. Rac1 appears to bind directly to mTOR and to mediate mTORC1 and mTORC2 localization at specific membranes. Binding of Rac1 to mTOR does not depend on the GTP-bound state of Rac1, but on the integrity of its C-terminal domain. This function of Rac1 provides a means to regulate mTORC1 and mTORC2 simultaneously. PMID:21474067

Comparison of carrier-added [99mTc] EDTMP and carrier-free preparations of [99mTc] EDTMP and [99mTc] DPD