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Sample records for bystrykh nejtronakh ibr-2

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

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    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

  2. Design and construction of a fast critical facility; Etude et construction d'un ensemble critique a neutrons rapides; Proektirovanie i sooruzhenie kriticheskoj sborki na bystrykh nejtronakh; Proyecto u construccion de un conjunto critico de neutrones rapidos

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    Kato, W Y; Dates, L R [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    estudiar las propiedades fisicas de los grandes reactores, altamente diluidos, de com- bustible metalico o ceramico, desprovistos de moderador o parcialmente moderados, con cuerpos de hasta 1500 l de volumen. Los autores describen detalladamente el ZPR-VI y analizan los criterios seguidos en el diseno de sus diversos componentes desde el punto de vista de la fisica de reactores. Asimismo, formulan algunas observaciones acerca de los procedimientos de explotacion y manejo del reactor, los peligros que se pueden presentar durante su funcionamiento, las tecnicas experimentales que conviene emplear y los costos de construccion. (author) [Russian] V programme razrabotki ehnergeticheskikh reaktorov na bystrykh nejtronakh kriticheskaya sborka yavlyaetsya ves'ma poleznym sredstvom dlya kontrolirovani ya vychislitel'nykh metodov, proverki sbornikov sechenij nejtronov i polucheniya vsekh parametrov reaktornoj fiziki, neobkhodimykh dlya proektirovaniya yadernoj ehnergeticheskoj sistemy. 'Poskol'ku ona yavlyaetsya prezhde vsego fizicheskoj sistemoj, proektirovanie kriticheskoj sborki stavit samo po sebe ryad trudnykh problem, ne vstrechayushchikhsya pri proektirovanii ehnergeticheskogo reaktora. Krome obychnykh voprosov, svyazannykh s mestoraspolozheniem , obolochkoj reaktora, raschetom aktivnoj zony i kontrol'no-izmeritel'nym i priborami, voznikayut takie problemy, kak dostizhenie vysokoj stepeni gibkosti, sovmestimoj s bezopasnost'yu, opredelenie razmerov i tipa ustanovki, udovletvoryayushchi kh trebovaniyam ehksperimental'noj fiziki, opredelenie chisla i razmeshcheniya reguliruyushchikh i avarijnykh sterzhnej, svodyashchikh k minimumu posledstviya vozmushchenij, i spetsifikatsiya vosproizvodimost i reguliruyushchikh sterzhnej i drugikh podvizhnykh komponentov s tem, chtoby obespechit' toch- nost', neobkhodimuyu pri izmereniyakh reaktivnosti. EHto lish' nekotorye iz problem, kotorye obsuzhdayutsya v nastoyashchem doklade, osnovannom na poslednem ehksperimente v Argonnskoj natsional

  3. Group cross-sections for fast reactors; Sections efficaces de groupes pour les reacteurs a neutrons rapides; Gruppovye secheniya reaktorov na bystrykh nejtronakh; Secciones eficaces de grupos para reactores rapidos

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    Zweifel, P P [University of Michigan, Ann Arbor, MI (United States); Ball, G L [Atomic Power Development Associates, Inc., Detroit, MI (United States)

    1962-03-15

    entre coeficientes de difusion de grupos, capacidad de moderacion y secciones eficaces de absorcion. Se demuestra que la definicion de las secciones eficaces de absorcion de grupos basada en integrales de resonancia eficaz que se emplea frecuentemente no es correcta, siendo preciso modificarla de acuerdo con el metodo de grupos multiples que se utilice. (author) [Russian] Daetsya obshchij obzor mnogogruppovykh diffuzionnykh uravnenij i rassmatrivaetsya pravil'naya forma gruppovykh poperechnykh sechenij. V chastnosti, pokazano, chto srednee poperechnoe sechenie perenosa mozhet do nekotoroj stepeni priblizitel'no byt' vyrazheno v vide srednej velichiny svobodnogo probega. Podschet takogo kolichestva zanimaet mnogo vremeni, tak kak on ne poddaetsya vyrazheniyu v vide ehlementarnogo usredneniya ; odnako podtverdilis' nekotorye neravnomernosti chto uproshchaet neobkhodimyj metod usredneniya. Rassmatrivayutsya tri sleduyushchikh voprosa gruppovykh poperechnykh sechenij, kotorye chasto ignoriruyutsya, no kotorye mogut imet' znachenie pri detal'nom izuchenii proekta : a) Ispol'zovanie odnoj i toj zhe serii usrednennykh po gruppam sechenij dlya vsekh reaktorov na bystrykh nejtronakh nichego ne daet, esli spektry razlichnykh reaktorov ne odinakovy i esli secheniya bystro izmenyayutsya v gruppe; takoe polozhenie chasto imeet mesto. Daetsya opisanie metoda povtoreniya, posredstvom kotorogo ustanavlivaetsya pravil'noe usrednenie, i ehtot metod ispol'zuetsya dlya opredeleniya vliyaniya spektral'nykh ehffektov na reaktornye raschety. b) Pri raschetakh perenosa, takikh, kak S{sub n} usredneniya dolzhny byt' vypolneny kak po uglu, tak i po ehnergii. Tak kak potok nel'zya razdelit' na 'uglovoj' i 'ehnergeticheskij', neobkhodimo ochen' tshchatel'no izbegat' oshibochnykh rezul'tatov. Uravnenie S{sub n} izuchaetsya v vide prostoj modeli, i poluchaetsya kriterij, kotoryj mozhet okazat'sya poleznym pri opredelenii znacheniya uglovoj nerazdelimosti v reaktornykh raschetakh. c) Na osnove

  4. Effect of the plutonium isotopic composition on the performance of fast reactors; Effet de la composition isotopique du plutonium sur le rendement de reacteurs a neutrons rapides; Vliyanie izotopnogo sostava plutoniya na rabotu reaktorov na bystrykh nejtronakh; Efectos de la composicion isotopica del plutonio sobre el funcionamiento de los reactores rapidos

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    Yiftah, S [Israel Atomic Energy Commission (Israel)

    1962-03-15

    fisionables por neutrones termicos ({sup 239}Pu y {sup 241}Pu), cuanto mas impuro sea el plutonio, tanto menor sera la masa critica y mayor la razon de reproduccion. Tomando como ejemplo el reactor de 1500 l, se comprobo ademas que al eliminar un 40 por ciento del sodio inicialmente presente en el cuerpo, la variacion de reactividad tiende a ser negativa a medida que aumenta la proporcion de isotopos superiores contenidos en el combustible de plutonio (en forma de metal, oxido o carburo). (author) [Russian] Izotopnyj sostav plutoniya, kotoryj dolzhen ispol'zovat'sya v kachestve goryuchego dlya reaktorov na bystrykh nejtronakh, budet zaviset' ot istochnika polucheniya plutoniya. V printsipe vozmozhny tri razlichnykh istochnika: a) proizvodyashchie reaktory; b) teplovye ehnergeticheskie reaktory (ispol'zuyushchie v kachestve topliva estestvennyj ili obogashchennyj uran); c) zony vosproizvodstv a reaktora na bystrykh nejtronakh. V osnovnom istochnik (a) i v nekotorom otnoshenii istochnik (s) budut davat' sravnitel'no 'chistyj' plutonij, t.e. glavnym obrazom plutonij-239, togda kak plutonij iz istochnika (b) budet 'gryaznym', t.e. plutoniem, bogatym izotopami plutoniya-240, plutoniya-241 i plutoniya-242. Stepen' 'zagryazneniya' budet zaviset' ot tipa reaktora, velichiny vygoraniya i voobshche ot istorii oblucheniya topliva. V takom sluchae voznikaet vopros, mozhno li ispol'zovat' v kachestve goryuchego dlya reaktorov na bystrykh nejtronakh lyubye vidy plutoniya. Dlya izucheniya vliyaniya razlichnogo izotopnogo sostava plutonievogo topliva v metallicheskom, oksidnom i karbidnom vide na rabotu reaktorov na bystrykh nejtronakh byli osushchestvleny ogranichennye serii podschetov po 16-gruppovoj diffuzionnoj teorii sfericheskoj geometrii s pomoshch'yu 16-gruppovogo komplekta poperechnykh sechenij, razrabotannogo nedavno Iftakhom, Okrentom i Mol'dauerom s ispol'zovaniem trekh razlichnykh vidov plutoniya, nachinaya s chistogo plutoniya-239 i povyshaya kolichestvo bolee vysokikh izotopov

  5. Integral physics data for fast-reactor design; Donnees de physique integrale intervenant dans les etudes de reacteur a neutrons rapides; Integral'nye fizicheskie dannye dlya raschetov reaktorov na bystrykh nejtronakh; Datos fisicos integrales para el diseno de reactores rapidos

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    Loewenstein, W B; Meneghetti, D [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    subcriticos, de las diversas magnitudes fisicas que presentan interes practico u/o teorico. Esas magnitudes fisicas caracterizan al sistema y permiten comprenderlo. Las mediciones mencionadas se refieren a la masa critica, el factor de forma del cuerpo, las razones de deteccion, los espectros neutronicos, los experimentos de sustitucion de materiales, la economia del reflector, la vida de los neutrones, el {alpha} de Rossi y otras magnitudes analogas. Los autores examinan estos datos y definen su campo de aplicacion. Demuestran que existen limites de validez para los resultados experimentales y analiticos en ciertos estudios espectrales y de criticidad. Proponen algunas investigaciones experimentales y analiticas que podrian constituir el objeto de futuros trabajos y que contribuirian a colmar la laguna entre la teoria y la experimentacion en los sistemas 'conocidos'. Al mismo tiempo, entre dichas investigaciones sugeridas se incluyen algunas tendientes a asentar sobre bases mas firmes la fisica de los modelos de reactores de potencia reproductores rapidos. (author) [Russian] Dlya sostavlennogo nedavno razdela o fizike reaktorov na bystrykh nejtronakh, kotoryj dolzhen vojti v vypuskaemoe vtoroe izdanie 'Postoyannye fiziki reaktorov', potrebovalos' sobrat' material po imeyushchimsya ehksperimental'ny m integral'nym dannym. Pri vklyuchenii v sostavlennyj razdel integral'nykh dannykh o fizike reaktorov na bystrykh nejtronakh, pomimo fakta ikh nalichiya, za osnovu byli vzyaty dva kriteriya: 1. ehti dannye polucheny iz otnositel'no prostykh sistem, kotorye pozvolyayut provodit' prostye teoreticheskie analizy; 2. slozhnye sistemy, kotorye yavlyayutsya prototipami ili modelyami, predstavlyayut osnovnoj interes dlya ehnergeticheskikh bystrykh reaktorov. Pervyj kriterij byl prinyat dlya togo, chtoby dat' perechen' integral'nykh dannykh takikh sistem, imeyushchikh ochen' obshchee primenenie dlya proverki parametrov secheniya i metodov raschetov. Vtoroj kriterij daet imeyushchiesya

  6. 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

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    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)

  7. Fission gas pressure build-up and fast-breeder economy; Accumulation de la pression des gaz de fission et economie des reacteurs surgenerateurs a neutrons rapides; Nakoplenie davleniya gazov produktov deleniya i ehkonomika reaktorov-razmnozhitelej na bystrykh nejtronakh; Aumento de la presion de los gases de fision y economia de los reactores reproductores rapidos

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    Engelmann, P [Kernforschungszentrum, Karlsruhe (Germany)

    1962-03-15

    materiales de alta resistencia, tales como el Inconel-X y el molibdeno pueden soportar la presion de los gases de fision a las temperaturas de funcionamiento corrientes. Desgraciadamente , la seccion eficaz de absorcion de estos materiales es superior a la del acero inoxidable. El autor presenta los resultados de calculos, realizados segun una teoria de varios grupos, que permite conocer el efecto de la utilizacion de estos materiales y de la disminucion de la densidad del combustible, sobre la masa critica y sobre la razon de reproduccion en los reactores reproductores de pequenas y medianas dimensiones. (author) [Russian] Na stoimost' toplivnogo tsikla i na vremya udvoeniya reaktorovbriderov na bystrykh nejtronakh sil'no vliyaet stepen' dostigaemogo vygoraniya topliva. Ispol'zovani e oksidnogo ili karbidnogo topliva daet vozmozhnost' dostignut' vygoraniya poryadka 100 000 mvt-n/t. V toplivnykh ehlementakh s pokrytiem ogranichivayushchi m faktorom yavlyaetsya rost gazov produktov deleniya. Pri rassmatrivaemo m vysokom vygoranii poddayushchayasya otsenke fraktsiya gazov, obrazuemykh pri delenii, popadaet v pory i tem samym uvelichivaet davlenie na obolochku. Iskhodya iz izvestnykh vykhodov produktov deleniya i tsepochek raspada bylo vychisleno kolichestvo obrazuyushchegosya gaza i sozdavaemoe im davlenie. Pri raschete davleniya, dejstvuyushchego na obolochku, byli ispol'zovany tri fizicheskikh modeli: i) gaz soderzhalsya v svyazanykh mezhdu soboj porakh, ii) v otdel'nykh porakh i iii) v tsentral'nom otverstii. Budet rassmotrena zavisimost' davleniya ot svobodnogo ob{sup e}ma (plotnost' topliva) i temperatury. Obolochki, izgotovlennye iz vysokoprochnykh materialov, naprimer, iz inkonelya-Kh i molibdena, mogli by vyderzhat' pri rabochikh temperaturakh davlenie gazov, vydelyayushchikhsya v rezul'tate deleniya. K sozhaleniyu, ehti materialy obladayut bolee vysokimi poperechnymi secheniyami pogloshcheniya, chem nerzhaveyushchaya stal'. Budut dany rezul'taty mnogogruppovog o

  8. Status of computational and experimental correlations for Los Alamos fast-neutron critical assemblies; Correlation entre les calculs et les experiences sur les ensembles critiques a neutrons rapides de Los Alamos; Sostoyanie vychislitel'nykh i ehksperimental'nykh korrelyatsij dlya Los-Alamosskoj kriticheskoj sistemy na bystrykh nejtronakh; Conjuntos criticos de neutrones rapidos de Los Alamos; correlacion entre resultados calculados y experimentales

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    Hansen, G E [Los Alamos Scientific Laboratory, University of California, Los Alamos, NM (United States)

    1962-03-15

    conjuntos de {sup 233}U en geometria esferica sin reflector o con un reflector constituido por una espesa capa de uranio. El autor expondra correlaciones directas entre los datos experimentales, para indicar que existe a priori la posibilidad de alcanzar correlaciones satisfactorias con los datos calculados. Tambien presentara, para diversos conjuntos tipicos y a fin de establecer los detalles de calculo necesarios la sensitividad de los espestros calculados y de los tamanos criticos a los modelos de transporte nsutronico (aproximaciones de transporte e hipotesis de proporcionalidad) y a las aproximacione s aritmeticas (hipotesis de la segmentacion angular finita y representacione s de grupos multiples). Las comparaciones entre los resultados experimentales y las evaluasiones se refieren a los indices espectrales y a los tamanos criticos, asi como a los periodos de semidesintegracion y a las razones correspondientes a los neutrones retardados. (author) [Russian] Novye sistemy i uluchshennaya izmeritel'naya tekhnika predusmatrivayu t periodicheskij peresmotr sostoyaniya vychislenij v zavisimosti ot ehksperimenta. Sleduet podcherknut' vazhnost' nejtronno-spektral'nykh kharakteristik iz-za osobenno trudnorazreshimykh problem, svyazannykhs absolyutnym izmereniem spektral'nykh indeksov i neobkhodimost'yu proverok vychislenij sverkh prostogo kriticheskogo razmera. Postoyannoe uluchshenie izmereniya spektral'nykh indeksov vmeste s uvelicheniem tochnosti kak mikroskopicheskikh dannykh dlya detektora i materialov sborok, tak i vychislitel'noj tekhniki, privodit k postepennomu proyasneniyu kharakteristik gruppy kriticheskikh sistem na bystrykh nejtronakh. Ehta gruppa sejchas vklyuchaet aktivnye zony s U{sup 233} bez otrazhatelya i s tolstym uranovym otrazhatelem. Pryamaya korrelyatsiya sredi ehksperimental'ny kh dannykh budet predstavlena s tsel'yu ukazat' predshestvuyushchi e vozmozhnosti dlya uspeshnykh korrelyatsij s vychisleniem. Budet predstavlena chuvstvitel

  9. The effective lifetime and temperature coefficient in a coupled fast-thermal reactor; Temps de vie effectif et coefficient de temperature dans un reacteur a couplage neutrons rapides-neutrons thermiques; Ehffektivnyj srok zhizni i temperaturnyj koehffitsient nejtronov v dvoyakom reaktore na bystrykh i teplovykh nejtronakh; Vida efectiva y coeficiente de temperatura en un reactor con acoplamiento rapido-termico

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    Haefele, W. [Kernforschungszentrum, Karlsruhe (Germany)

    1962-03-15

    . Teplovoj komponent dejstvuet kak svoego roda zamedlitel' vremeni zhizni nejtronov. Kak i v teorii zapazdyvayushchikh nejtronov, ehffekt zapazdyvaniya ischezaet, esli reaktivnost' dostatochno vysoka, chtoby bystryj komponent stal kritichnym sam po sebe. V issledovanii rassmatrivalsya sparennyj reaktor, v kotorom bystryj komponent podvergaetsya dejstviyu vnezapnogo stupenchatogo skachka reaktivnosti {alpha}{sub 0}. Izza vozrastayushchego urovnya ehnergii temperatura podnimaetsya i nachinayut rabotat' dva temperaturnykh koehffitsienta: temperaturnyj koehffitsient bystrogo komponenta i temperaturnyj koehffitsient teplovogo komponenta. Ehta problema rassmatrivaetsya s odnoj gruppoj zapazdyvayushchikh nejtronov (v obychnom znachenii). Privoditsya formalizm dlya vyrazheniya ehffektivnogo sroka zhizni i temperaturnogo koehffitsienta vo vremya razlichnykh stadij issledovaniya. Dany takie otkloneniya dlya razlichnykh znachenij {alpha}{sub 0}, pri kotorykh dostigaetsya predel kinetiki reaktorov na bystrykh nejtronakh. (author)

  10. Major accident analyses for experimental zero-power fast reactor assemblies; Analyse des accidents graves pouvant survenir dans les reacteurs experimentaux a neutrons rapides de puissance zero; Analiz krupnoj avarii dlya ehksperimental'ny kh reaktornykh ustanovok nulevoj moshchnosti na bystrykh nejtronakh; Analisis de los accidentes graves que pueden producirse en los reactores experimentales rapidos de potencia cero

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    Fischer, G.; Barts, E. W.; Kapil, S.; Tomabechi, K. [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    autores explican como han adaptado la clave AX-I para calculos neutronico-hidro-dinamicos al caso de un gas que se ajusta a la ecuacion de Van der Waals. Otra modificacion importante introducida en la ecuacion de estado utilizada en la clave, consiste en emplear una ecuacion del tipo de Mie-Gruneisen, derivada de la teoria del estado solido. Esta modificacion permite evaluar de manera mas satisfactoria del termino de presion para el caso de cuerpos de composicion variable. Dado que en un conjunto de potencia cero las placas de uranio fuertemente enriquecido en el isotopo-235, se calentaran con mas rapidez que las de uranio empobrecido, la posibilidad de que se produzca un efecto Doppler positivo neto es mucho mayor en un conjunto experimental que en el reactor de potencia reproductor equivalente. Se ha estudiado este peligro en el caso de diferentes conjuntos posibles. Los calculos indican que en un conjunto de potencia cero el coeficiente Doppler solo alcanza un valor peligroso en los sistemas que poseen un espectro de energias neutronicas muy blando, caracteristico de los grandes reactores de potencia reproductores, alimentados con oxido de uranio. (author) [Russian] Provedeno issledovanie vozmozhnosti, mekhanizma i posledstvij rasplavleniya, a takzhe drugikh krupnykh yadernykh intsidentov dlya ehksperimental'nog o reaktora nulevoj moshchnosti na bystrykh nejtronakh tipa ZPR-III dvukhpolovinchatog o tipa. V dopolnenie k ehtomu issledovaniyu provedena otsenka znacheniya ehffekta Dopplera dlya mnogikh yadernykh reaktornykh ustanovok takogo reaktora. V doklade budet pokazano, chto yavlenie rasplavleniya maloveroyatno vvidu ogranichennogo kolichestva yavlenij, kotorye nuzhno postulirovat'. Posle rassmotreniya mekhanizma razrusheniya budut dany rezul'taty raschetov, svyazannykh s nejtronnoj fizikoj i gidro-dinamikoj , dlya dvukh reaktornykh ustanovok nulevoj moshchnosti. Provedeno issledovanie aktivnoj zony emkost'yu 1200 litrov, kharakternoj dlya otnositel'no bol

  11. Selected topics in research program on the IBR-2

    International Nuclear Information System (INIS)

    Luschikov, V.I.; Pikelner, L.B.; Popov, Yu.P.; Frank, I.M.; Sharapov, E.I.; Yazvitskii, Yu.S.

    1979-01-01

    The physical parameters of the IBR-2 fast pulsed reactor and research programs carried out on the reactor are described. Design values for an instantaneous thermal neutron fluxes are: 10 17 and 10 16 cm -2 s -1 inside and from the surface of the moderator respectively. In combination with the heavy current, short pulse injector (electron induction accelerator LIU-30 being under construction now) it will become a unique neutron source for the time-of-flight investigations in the energy range from 10 -7 to 10 6 eV. The characteristics of the complex IBR-2 + LIU-30 are described. The neutron beams are numbered and their use in the condensed matter and applied research is mentioned. The program for the experiments on the IBR-2 connected with nα, nγ and nf cross section measurements as well as neutron cross section study for few nucleon systems are reported. The prospects for nuclear physics research on the LIU-30 nonmultiplying target facility are outlined using as examples the experiments with polarized neutrons and nuclei and some others. The description is illustrated with the results obtained recently on the IBR-30 operating pulsed reactor

  12. Analytical investigations at the IBR-2 reactor in Dubna

    International Nuclear Information System (INIS)

    Frontas'eva, M.V.; Pavlov, S.S.

    2000-01-01

    Experience in applying activation analysis with epithermal neutrons to environmental studies at the IBR-2 pulsed fast reactor in Dubna is reviewed. The principal units of the pneumatic system REGATA are described as well as the main present-day parameters of the irradiation channels. Examples from two challenging areas: analysis of airborne particulate matter and analysis of the biomonitors of atmospheric deposition, where the feasibility of ENAA related to non-nuclear multi-element techniques has been shown, are given. ENAA is presently being used in several projects carried out at FLNP JINR that involve the analysis of aerosol filters. For these studies, instrumental neutron activation analysis cannot feasibly be replaced by any non-nuclear analytical technique at the present state of art due to the fact that the total mass of the aerosol collected on filter samples is often rather small. This favours direct instrumental techniques rather than those depending on dissolving the sample prior to analysis. The dominant part of air pollution studies at FLNP JINR is based on the use of the moss biomonitoring technique resulting in a final product-maps of the atmospheric deposition of heavy metals, rare-earths, actinides (U and Th), etc., constructed by the GIS (geographical information system) technology

  13. New developments of TOF neutron diffraction at the IBR-2 pulsed reactor

    International Nuclear Information System (INIS)

    Balagurov, Anatoli M.

    2001-01-01

    Development of high-resolution RTOF Fourier technique for powder neutron diffraction studies is being continued at the IBR-2 pulsed reactor in Dubna. Besides some technical improvements in the operating HRFD instrument, a new dedicated instrument, Fourier Strain Diffractometer (FSD), for investigation of residual stresses in bulk materials has been constructed at IBR-2 in 1999. With a new HRFD Fourier chopper smaller than 10 μs TOF contribution in a resolution function was obtained in the experiment with perfect Si single crystal. A series of diffraction experiments with the beams from a new methane cold neutron moderator installed at the IBR-2 in 1999 is discussed. A comparison with the results obtained with the conventional water comb-like moderator shows that for various types of experiments, which are performed at HRFD and DN-2 diffractometers, the methane cold neutron source provides better conditions. (author)

  14. Current state and prospects of the IBR-2M instrument control software

    International Nuclear Information System (INIS)

    Kirilov, A.S.

    2011-01-01

    The article is devoted to the main features and plans of future improvements of the Sonix + instrumental complex, which is used now to control experimental hardware at the IBR-2M spectrometers. The Sonix + software inherited basic solutions from the older Sonix system. In particular, those are the modular organization using special database for device control and reflection of the current system state, using script programming for the measured procedure. At the same time, some basic features were revised to make the system more unified, flexible and comfortable for the user. Main changes can be grouped as follows: structural enhancements, using the Python as a script language, GUI redesign and unification, remote supervision and instrument control via network. During the last years, this complex has been tested at some IBR-2 instruments (REMUR, NERA-PR) and on some instruments at other centers. We are planning to install it at the other instruments of IBR-2M as well

  15. Estimation of power feedback parameters of pulse reactor IBR-2M on transients

    International Nuclear Information System (INIS)

    Pepyolyshev, Yu.N.; Popov, A.K.

    2013-01-01

    Parameters of the IBR-2M reactor power feedback (PFB) on a model of the reactor dynamics by mathematical treatment of two registered transients are estimated. Frequency characteristics and the pulse transient characteristics corresponding to these PFB parameters are calculated. PFB parameters received thus can be considered as their express tentative estimation as real measurements in this case occupy no more than 30 minutes. Total PFB is negative at 1 and 2 MW. At the received estimations of PFB parameters in a self-regulation mode it is possible to consider the stability margins of the IBR-2M reactor satisfactory

  16. The new fourier diffractometer at the IBR-2 reactor: design and first results

    International Nuclear Information System (INIS)

    Aksenov, V.L.; Balagurov, A.M.; Simkin, V.G.

    1992-01-01

    A high-resolution neutron powder Fourier diffractometer has been constructed at the pulsed reactor IBR-2 in Dubna. Preliminary results have confirmed resolution predictions indicating that Δd/d can be as small as 5x10 -4 over a wide d range with a good data accumulation rate. 3 refs.; 10 figs.; 1 tab

  17. Recent Development of Radioanalytical Methods at the IBR-2 Pulsed Fast Reactor

    International Nuclear Information System (INIS)

    Nazarov, V.M.; Peresedov, V.F.

    1994-01-01

    Experience in the application of radioanalytical methods, including NAA, at the IBR-2 pulsed fast reactor is reviewed. Details of the instruments dedicated to neutron activation analysis and radiography studies are reported. Applications of resonance neutrons to environmental monitoring and to the investigation of high-purity materials, are examplified. 15 refs. 9 figs., 9 tabs

  18. Distribution of energy of impulses of the modernized IBR-2 REACTOR

    International Nuclear Information System (INIS)

    Tayibov, L.A; Mehtiyeva, R.N.; )

    2011-01-01

    Full text: For the modernized IBR-2 reactor there are two main reasons causing fluctuations of energy of impulses [1,3] on low power of stochastic fluctuations, on the nominal - giving rise to fluctuations of external reactance. The fluctuations of pulse energy is quite significant (20%). They affect the dynamics of the reactor, the process of regulation, starting, as well as the work of the experimental apparatus, etc. It is clear that research of fluctuation of energy of impulses has special value for the IBR-2 type reactor. Sufficient information about the statistical properties of the reactor noise gives the density distribution of the energy pulse power. We used the usual procedure of statistical analysis of time series. Calculated pulse energy of density and the parameters of this distribution.

  19. Estimation of power feedback parameters of the IBR-2M reactor by square wave reactivity

    International Nuclear Information System (INIS)

    Pepelyshev, Yu.N.; Popov, A.K.; Sumkhuu, D.

    2016-01-01

    Parameters of the IBR-2M reactor power feedback (PFB) are estimated based on the analysis of power transients caused by deliberate square wave reactivity when the pulsed reactor operates in the self-regulation mode. The PFB of the IBR-2M is described by three linear first-order differential equations. Two components of the PFB are responsible for the negative feedback and one, for the positive. The overall feedback is negative, i.e., it has a stabilizing effect for the operation of the reactor. The slowest negative component of the PFB is probably caused by heating of the fuel. Periodically repeated in the process of exploitation, estimation of the PFB parameters is one of the methods to ensure safety operation of the reactor. [ru

  20. Statistical analysis for the pulse energy fluctuations of the IBR-2M reactor

    International Nuclear Information System (INIS)

    Morkovnikov, I.A.; Ivankov, O.I.; Kirilov, A.S.

    2012-01-01

    The work is dedicated to the automation of the registration process of measurements performed on the IBR-2 instruments. Stored information is intended for those responsible for the instruments, in order to simplify measurements accounting, provide information search and assist in the preparation of reports. The general approach to the problem is considered, which in the first phase was implemented on YuMO spectrometer using Python, PyQt, MySQL

  1. Status and perspective of development of cold moderators at the IBR-2 reactor

    International Nuclear Information System (INIS)

    Kulikov, S; Shabalin, E

    2012-01-01

    The modernized IBR-2M reactor will start its operation with three water grooved moderators in 2011. Afterwards, they will be exchanged by a new complex of moderators. The complex consists of three so-called kombi-moderators, each of them containing a pre-moderator, a cold moderator, grooved ambient water moderators and post-moderators. They are mounted onto three moveable trolleys that serve to deliver and install moderators near the reactor core. The project is divided in three stages. In 2012 the first stage of development of complex of moderators will be finished. The water grooved moderator will be replaced with the new kombi-moderator for beams nos. 7, 8, 10, 11. Main parameters of moderators for this direction will be studied then. The next stages will be done for beams nos. 2-3 and for beams nos. 1, 9, 4-6, consequently. Cold moderator chambers at the modernized IBR-2 reactor are filled with thousands of beads (∼3.5 - 4 mm in diameter) of moderating material. The cold helium gas flow delivers beads from the charging device to the moderator during the fulfillment process and cools down them during the reactor cycle. The mixture of aromatic hydrocarbons (mesithylen and m-xylen) has been chosen as moderating material. The explanation of the choice of material for novel cold neutron moderators, configuration of moderator complex for the modernized IBR-2 reactor and the main results of optimization of moderator complex for the third stage of moderator development are discussed in the article.

  2. Status and perspective of development of cold moderators at the IBR-2 reactor

    Science.gov (United States)

    Kulikov, S.; Shabalin, E.

    2012-03-01

    The modernized IBR-2M reactor will start its operation with three water grooved moderators in 2011. Afterwards, they will be exchanged by a new complex of moderators. The complex consists of three so-called kombi-moderators, each of them containing a pre-moderator, a cold moderator, grooved ambient water moderators and post-moderators. They are mounted onto three moveable trolleys that serve to deliver and install moderators near the reactor core. The project is divided in three stages. In 2012 the first stage of development of complex of moderators will be finished. The water grooved moderator will be replaced with the new kombi-moderator for beams #7, 8, 10, 11. Main parameters of moderators for this direction will be studied then. The next stages will be done for beams #2-3 and for beams #1, 9, 4-6, consequently. Cold moderator chambers at the modernized IBR-2 reactor are filled with thousands of beads (~3.5 - 4 mm in diameter) of moderating material. The cold helium gas flow delivers beads from the charging device to the moderator during the fulfillment process and cools down them during the reactor cycle. The mixture of aromatic hydrocarbons (mesithylen and m-xylen) has been chosen as moderating material. The explanation of the choice of material for novel cold neutron moderators, configuration of moderator complex for the modernized IBR-2 reactor and the main results of optimization of moderator complex for the third stage of moderator development are discussed in the article.

  3. Recent development of radioanalytical method at IBR-2 pulsed fast reactor of the JINR

    International Nuclear Information System (INIS)

    Nazarov, V.M.; Pavlov, S.S.; Herrera, E.

    1991-01-01

    The experience of the use of radioanalytical methods, including NAA at IBR-2 pilsed fast reactor of the JINR, is discussed. Physical and technical parameters of the experimental installation designed for NAA and radiography are given. The detailed examples of the application of resonance neutrons to the control of the environment in the geology of oil, in multi-element analysis of food products and superpure materials as well as in nuclear physics are reviewed. The works on the application of the neutron isotopes sources for express determination of nitrogen content in original and synthetic materials are introduced. 7 refs.; 8 figs.; 3 tabs

  4. Pelletized cold moderator of the IBR-2 reactor: current status and future development

    International Nuclear Information System (INIS)

    Ananiev, V; Beliakov, A; Bulavin, M; Verkhogliadov, A; Kulagin, E; Kulikov, S; Mukhin, K; Shabalin, E; Loktaev, K

    2016-01-01

    Current status and future development of the pelletized cold moderator of the IBR-2 reactor in Neutron Physics Laboratory of JINR are represented. Nowadays cold moderator works for physical experiments and allows conducting experiments in the region of wavelengths more than 4 Å up to 10-13 times faster in comparison with the warm water moderator. Future development of the pelletized cold moderator is aimed at increasing the time of its operation for experiments and is based on three components: creation of a system of continuous charging and discharging of beads, supplementation of various additives, and use of new materials, such as triphenylmethane. (paper)

  5. Power noise spectrum classification in the problem of the IBR-2 reactor

    International Nuclear Information System (INIS)

    Bargel, M.; Kitowski, J.; Pepelyshev, Yu.N.

    1988-01-01

    The classification spectrum results of random fluctuations in the IBR-2 energy pulse are presented. The work is performed for the application of the obtained results to the reactor diagnostics and the study of its noise uncontrolled states. For classification of the spectra the method of pattern recognition based upon the ISODATA heuristic algorithm is used. It is shown that a set of noise uncontrolled reactor states, registered during the reactor operation period at power of 0.4-2 MVt with the first variant of moving reflector (1983-1986) is formed into 4(5) most typical states. Each of the states corresponds to the general conditions of the reactor core cooling and provides the normal work of the moving reflector. However, these states differ in coolant flow, power level and peculiarities of the moving reflector rotation regime. One type of anomal power noise, connected with some disorder in the moving reflctor work, is isolated. This work also presents the possibility of control over the state of moving reflectors according to the change in the amplitude of power oscillations at some frequences. The reactor noise classification results can be used as the data bank for the IBR-2 reactor diagnostic system

  6. Neutron diffraction potentialities at the IBR-2 pulsed reactor for nondestructive testing of structural materials

    International Nuclear Information System (INIS)

    Balagurov, A.M.; Bokuchava, G.D.; Papushkin, I.V.; Sumin, V.V.; Venter, A.M.

    2010-01-01

    Neutron diffraction is widely used for investigations of residual and applied stresses in bulk materials and components. The most important factor in these investigations is the high penetration depth of neutrons (up to 2 cm for steel). At the IBR-2 pulsed reactor in Dubna the Fourier stress diffractometer (FSD) has been constructed to optimize the internal stress measurements. The FSD design satisfies the requirements of high luminosity, high resolution and specific sample environment. The collimator system guarantees a minimum gauge volume of 2x2x2 mm. A mechanical testing machine allows in-situ tension or compression measurements up to a load of 20 kN and sample temperatures up to 800 deg C. In the paper the current status of FSD is reported and potentialities are demonstrated with several examples of investigations performed

  7. Studies of electrochemical interfaces by TOF neutron reflectometry at the IBR-2 reactor

    Science.gov (United States)

    Petrenko, V. I.; Gapon, I. V.; Rulev, A. A.; Ushakova, E. E.; Kataev, E. Yu; Yashina, L. V.; Itkis, D. M.; Avdeev, M. V.

    2018-03-01

    The operation performance of electrochemical energy conversion and storage systems such as supercapacitors and batteries depends on the processes occurring at the electrochemical interfaces, where charge separation and chemical reactions occur. Here, we report about the tests of the neutron reflectometry cells specially designed for operando studies of structural changes at the electrochemical interfaces between solid electrodes and liquid electrolytes. The cells are compatible with anhydrous electrolytes with organic solvents, which are employed today in all lithium ion batteries and most supercapacitors. The sensitivity of neutron reflectometry applied at the time-of-flight (TOF) reflectometer at the pulsed reactor IBR-2 is discussed regarding the effect of solid electrolyte interphase (SEI) formation on metal electrode surface.

  8. Experimental estimations of the kinetics parameters of the IBR-2M reactor by stochastic noises

    International Nuclear Information System (INIS)

    Pepelyshev, Yu.N.; Tajybov, L.A.; Garibov, A.A.; Mekhtieva, R.N.

    2012-01-01

    Experimental investigations of stochastic fluctuations of pulse energy of the IBR-2M reactor have been carried out which allowed us to obtain some of the parameters of the reactor kinetics. At different levels of average power a sequence of values of pulse energy was recorded with the calculation of the distribution parameters. An ionization chamber with boron installed near the active zone was used as a neutron detector. The research results allowed us to estimate the average lifetime of prompt neutrons τ = (6.53±0.2)·10 -8 s, absolute power of the reactor and intensity of the source of spontaneous neutrons S sp ≤(6.72±0.12)·10 6 s -1 . It was shown that the experimental results are close to the calculated ones

  9. Model study of an automatic controller of the IBR-2 pulsed reactor

    International Nuclear Information System (INIS)

    Pepelyshev, Yu.N.; Popov, A.K.

    2007-01-01

    For calculation of power transients in the IBR-2 reactor a special mathematical model of dynamics taking into account the discontinuous jump of reactivity by an automatic controller with the step motor is created. In the model the nonlinear dependence of the energy of power pulse on the reactivity and the influence of warming up of the reactor on the reactivity by means of introduction of a nonlinear feedback 'power-pulse energy - reactivity' are taken into account. With the help of the model the transients of relative deviation of power-pulse energy are calculated at various (random, mixed and regular) reactivity disturbances at the reactor mean power 1.475 MW. It is shown that to improve the quality of processes the choice of such regular values of parameters of the automatic controller is expedient, at which the least effect of smoothing of a signal acting on an automatic controller and the least speed of an automatic controller are provided, and the reduction of efficiency of one step of the automatic controller and introduction of a five-percent dead space are also expedient

  10. First experience with the new solid methane moderator at the IBR-2 reactor

    International Nuclear Information System (INIS)

    Beliakov, A.A.; Shabalin, E.P.; Tretyakov, I.T.

    2001-01-01

    In the 1999 Fall the solid methane moderator (CM) has been installed and tested at full power at the IBR-2 pulsed reactor. Its main features are a beryllium reflector and a light water premoderator. Radiation load on the methane was three times as much as that of IPNS facility, namely, 0.1 W/g. Effects of temperature, operation time, concentration of a hydrogen scavenger, and annealing procedure on both neutron and service performances were studied. Maximum operation time of a newly loaded portion of methane was 4 days. In this time around 30% of methane is transformed into hydrogen, ethane, and high molecular hydrocarbons, and yet no deterioration in cold neutron intensity was detected. Among new knowledge, the most important are two facts observed: two-fold decrease in hydrogen formation rate when methane is poisoned with 2.5% to 5% of ethylene, and low formation rate of solid, inremovable products of radiolysis - (1.5/3)10 -7 g/J, which means that after 10 years of operation the methane chamber will be filled with only 100 g of residue. Gain of factor 20 in cold neutron flux was obtained as compared to the routine grooved light water moderator. Presently, it is the highest among the intense pulsed neutron sources. (author)

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

    CERN Document Server

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

    1998-01-01

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

  12. Organization of remote control of spectrometers at the IBR-2M reactor

    International Nuclear Information System (INIS)

    Kirilov, A.S.; Murashkevich, S.M.; Okulov, R.Yu.; Petukhova, T.B.

    2008-01-01

    The development of network infrastructure in Dubna creates conditions for the remote supervision/control of experiment at the IBR-2M reactor beyond the JINR local network. The opportunity of observing an experiment from outside makes it possible to respond to errors or unforeseen, to save the reactor time. The principles of organization and peculiarities of implementation of the WebSonix system consisting of the central web-site and communication facilities for spectrometers are considered in the paper. The system allows one to reflect the actual condition of all the components of the instrument, survey log files, visualize the accumulated spectra and to control the experimental procedure on the instruments controlled by the software complex Sonix+ (OS Windows XP). The system is an independent instrument, it is easy to extend or change and easy to adapt to the instrument data specifics. The system is implemented using the PHP and Python scripts. The OS GNU/Linux Debian and web-server Apache 2 are installed on the web-site computer

  13. Measurement of cold neutron spectra at a model of cryogenic moderator of the IBR-2M reactor

    International Nuclear Information System (INIS)

    Kulikov, S.A.; Chernikov, A.N.; Shabalin, E.P.; Kalinin, I.V.; Morozov, V.M.; Novikov, A.G.; Puchkov, A.V.

    2010-01-01

    The article is dedicated to methods and results of experimental determination of cold neutron spectra from solid mesitylene at neutron moderator temperatures 10-50 K. Experiments were fulfilled at the DIN-2PI spectrometer of the IBR-2 reactor. The main goals of this work were to examine a system of constants for Monte Carlo calculation of cryogenic moderators of the IBR-2M reactor and to determine the temperature dependence of cold neutron intensity from the moderator. A reasonable agreement of experimental and calculation results for mesitylene at 20 K has been obtained. The cold neutron intensity at temperature of moderator 10 K is about 1.8 times higher than at T=50 K

  14. An experiment on the investigation of the possibilities of the detection of heated UCN at the IBR-2

    International Nuclear Information System (INIS)

    Kalchev, S.D.; Strelkov, A.V.

    1990-01-01

    An experiment on the investigation of the heating of ultracold neutrons (UCN) in the reactor IBR-2 is described. By measuring the flux of thermal neutrons (upscattered UCN heated on polyethylene) the UCN flux density in a neutron guide is estimated to be approx. 25 cm -2 s -1 . The paper reports on the analysis of the background of a counter of heated neutrons. 9 refs.; 5 figs

  15. Perspectives and possibilities for solid state physcis investigations at thhe pulsed reactor IBR-2 of the JINR Dubna

    International Nuclear Information System (INIS)

    Feldmann, K.; Frauenheim, T.; Lauckner, J.; Weniger, J.; Muehle, E.

    1982-02-01

    Three time-of-flight spectrometers (spectrometer of high resolution NSWR, spectrometer of inverted geometry KDSOG and spectrometer of polarized neutrons SPN-1) are presented, which will be working at the pulsed IBR-2 reactor of the JINR Dubna. Considering the parameters and the special methods of measurement of these spectrometers, the possibilities of their applications for the investigations of structural, magnetic and electronic properties of solids by means of elastic, inelastic and quasielastic neutron scattering are discussed. (author)

  16. The system for diagnostics and monitoring of the IBR-2 reactor state. Data acquisition, accumulation and storage of information

    International Nuclear Information System (INIS)

    Ermilov, V.G.; Ivanov, V.V.; Korolev, V.S.; Pepelyshev, Yu.N.; Semashko, S.V.; Tulaev, A.B.

    2000-01-01

    The architectural decisions for a developed distributed system of the IBR-2 pulsed reactor conditions monitoring are described. The system is intended for measurement of the basic reactor parameters, acquisition, storage and processing of information, the current reactor state monitoring, analysis of reactor parameters for a long time operation period both in on-line, and in off-line modes. The system is constructed in the architecture client-server using DBMS MS SQL Server 7.0 The basic hardware components of the system are measuring workstations and devices, processing and user workstations and the central server. The software of the system consists of the measuring programs, data flows dispatching services, client applications for data processing and visualization, and means for preparing data for subsequent presentation in WWW. The basic results of the first system operation phase and prospect of its development are discussed. (author)

  17. Control system of executive mechanisms of a spectrometer on the IBR-2 reactor as a modern local network of controllers CAN

    International Nuclear Information System (INIS)

    Zhuravlev, V.V.; Kirillov, A.S.; Petukhova, T.B.; Sirotin, A.P.

    2007-01-01

    Controllers SMC-32 and SMC-32-CAN as elements of control systems of executive mechanisms of the IBR-2 spectrometers are submitted. The controllers provide management of executive mechanisms of spectrometers on the consecutive communication line RS232, RS422 (SMC-32, SMC-32-CAN), and on the local network CAN (SMC-32-CAN). The control systems of the executive mechanisms are easily modernized due to connection of additional elements of the local network CAN. Dynamic characteristics of the spectrometers' executive mechanisms are essentially improved. For example, it has been possible to increase the rotation frequency of the step motor DSHI-200 up to 10000 pps. (author)

  18. Excitation of 107m,109m Ag isomeric states in the fast neutron inelastic scattering at the Ibr-2 reactor of JINR

    International Nuclear Information System (INIS)

    Alpatov, V.G.; Davydov, A.V.; Isaev, Yu.N.

    1997-01-01

    The excitation cross sections of long-living isomers of 107m,109m Ag nuclei were measured for the fast neutron inelastic scattering reactions at the Ibr-2 reactor of JINR (Dubna) by means of a comparison with the yield of the 103m Rh isomer. The excitation cross sections of the latter are known for analogous reactions in the wide energy range. The measured cross sections are the following: σ( 107m Ag) 204 ± 18 mb, σ( 109m Ag) = 262 ± 26 mb. These values are essentially lower than the excitation cross section of the 103m Rh isomer. The analysis of the data on level structures and transitions between these levels for rhodium and silver nuclei together with the data on γ-spectra created in the reactions (n, n ' γ) shows that the essential difference between excitation cross sections of Rh and Ag isomers can be explained by different populations of corresponding levels

  19. A critical summary of microscopic fast-neutron interactions with reactor structural, fissile and fertile materials; Apercu critique des interactions microscopiques des neutrons rapides avec les materiaux de construction et les matieres fissiles et fertiles utilisees dans les reacteurs; Kriticheskij obzor mikroskopicheskog o vzaimodejstviya bystrykh nejtronov s konstruktsionnymi, rasshcheplyayushchimis ya i vosproizvodyashchim i reaktornymi materialami; Resumen critico de las interacciones microscopicas de los neutrones rapidos con los materiales estructurales fisionables y fertiles utilizados en los reactores

    Energy Technology Data Exchange (ETDEWEB)

    Smith, A B [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    doklade, ne tol'ko mogut byt' primeneny s bol'shoj pol'zoj, no i sami yavlyayutsya primerom primeneniya peredovoj ehksperimental'no j yadernoj tekhniki. Ukazyvayutsya oblasti, v kotorykh ehksperimental'ny e dannye libo nedostatochny, libo protivorechivy, libo voobshche otsutstvuyut. Delaetsya prognoz v otnoshenii budushchikh znanij o reaktsiyakh na bystrykh nejtronakh i podcherkivaetsya neobkhodimost' vypolneniya reaktornykh trebovanij dlya polucheniya osnovnykh yadernykh dannykh. (author)

  20. The determination of sulphur in materials of high neutron absorption cross-section by fast-neutron activation analysis; Determination du soufre dans les matieres de forte section efficace d'absorption neutronique, au moyen d'une analyse par activation avec des neutrons rapides; Opredelenie sery v materialakh s bol'shim secheniem pogloshcheniya nejtronov metodom aktivatsionnogo analiza bystrykh nejtronov; Determinacion del azufre en sustancias de elevada seccion eficaz de absorcion neutronica mediante analisis por activacion con neutrones rapidos

    Energy Technology Data Exchange (ETDEWEB)

    Gibbons, D; Simpson, H [Wantage Research Laboratory (A.E.R.E.), Wantage, Berks. (United Kingdom)

    1962-01-15

    secciones eficaces de absorcion para los neutrones rapidos son mucho mas bajas que para los lentos lo cual reduce considerablemente los errores debidos al autoblindaje. La interferencia debida a la reaccion (n, {gamma}) causada por los neutrones lentos en el fosforo natural puede eliminarse gracias a una tecnica que consiste en efectuar irradiaciones dobles en regiones del reactor en que varien las razones del flujo de neutrones lentos a neutrones rapidos. El metodo se ha aplicado a la determinacion del azufre en cromo y arsenico. (author) [Russian] Proizvodstvo radiofosfora pri vzaimodejstvii bystrykh nejtronov (n, p) s seroj ispol'zuetsya dlya opredeleniya sery s pomoshch'yu aktivatsionnogo analiza. Ispol'zovanie dannogo metoda pozvolyaet opredelit' nalichie sery v materialakh s bol'shim secheniem pogloshcheniya teplovykh nejtronov, t.k. sechenie pogloshcheniya bystrykh nejtronov, kak pravilo, znachitel'no men'she, chem medlennykh nejtronov, chto pozvolyaet zametno snizit' veroyatnost' oshibok iz-za samozashchity. Pomekhi iz-za reaktsii (n, {gamma}) na medlennykh nejtronakh s estestvennym fosforom ustranyayutsya metodom dvojnogo oblucheniya v mestakh s razlichnym otnosheniem potokov bystrykh i medlennykh nejtronov. Dannyj metod primenyalsya dlya opredeleniya sery v khrome i mysh'yake. (author)

  1. 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

    The design of a two-halves zero-energy fast reactor is briefly described, particular emphasis being placed on those features which determine the practicability and precision of reactor physics measurements. The advantages and disadvantages of the design are discussed with reference to the two years' operating experience of the reactor. The following topics are dealt with: the experimental convenience of the lay-out and of the two halves design; the size and precision of the fuel pieces and the accuracy of location of the fuel elements; the effects of edge irregularities and heterogeneity of structure on the accuracy with which the critical mass of an 'ideal' equivalent assembly is determined; reproducibility of the critical condition after dismantling the assembly, or separating the two halves; variation of reactivity with separation of the halves, including effects of asymmetric loading; sensitivity of various counters, neutron source strength, use of an accelerator neutron source; speed of response of safety circuits and consequent restrictions on rate of assembly of the two halves; additional precautions necessary in using plutonium fuel; and notes on the accuracy of measurement of reactivity and on the practical limitations affecting various other reactor physics measurements. (author) [French] Les auteurs decrivent brievement ce modele de reacteur a neutrons rapides et de puissance zero construit en deux moities, en insistant particulierment sur les caracteristiques qui determinent la possibilites de faire des mesures relatives a la physique des reacteurs et la precision de ces mesures. Ils exposent les avantages et les inconvenients de ce modele compte tenu de l'experience acquise au cours des deux annees de fonctionnement du reacteur. Ils traitent les sujets suivants: interet pratique, au point de vue experimental, du plan de ce reacteur et de sa constitution en deux moities; dimension et precision des pieces de combustible et exactitude de l'emplacement des elements combustibles; incidences des irregularites des faces et de l'heterogeneite de la structure sur l'exactitude avec laquelle on determine la masse critique d'un assemblage equivalent 'ideal'; possibilite de reproduire l'etat critique apres avoir demonte l'assemblage ou separe les deux moities; variation de la reactivite lors de la separation des deux moities, et effets d'un chargement asymetrique; sensibilite de divers compteurs, intensite de la source de neutrons, utilisation d'un accelerateur comme source de neutrons; vitesse de reponse des circuits de securite et restrictions qu'elle peut entrainer pour la vitesse d'assemblage des deux moities; precautions supplementaires qu'il faut prendre pour utiliser le plutonium comme combustible; notes sur l'exactitude des mesures de la reactivite et sur les limitations d'ordre pratique imposees a diverses autres mesures en physique des reacteurs. (author) [Spanish] Los autores describen brevemente las caracteristicas de un reactor rapido de potencia nula de dos mitades, en especial las que determinan la posibilidad de efectuar mediciones de precisidn en la esfera de la fisica de los reactores. Examinan las ventajas e inconvenientes de este tipo de reactor, basandose en la experiencia adquirida durante dos anos de funcionamiento. Exam in an los siguientes temas: ventajas, desde el punto de vista experimental, de la disposicion y de la construccidn en dos mitades; dimensiones y tolerancias de los elementos combustibles, y precisian con la que se puede determinar la posicion de dichos elementos; influencia de las irregularidades marginales y de heterogeneidad estructural sobre la exactitud con la que se determine la masa critica de un conjunto 'ideal' equivalente; posibilidad de reproducir las condiciones criticas despues de desmontar el conjunto o de separar las dos mitades; variaciones de la reactividad cuando se separan las dos mitades, en especial los efectos de una carga asimetrica; sensibilidad de varios contadores, 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)

  2. Excitation of 107m,109mAg isomeric states in the inelastic scattering of fast neutrons from the IBR-2 reactor of JINR

    International Nuclear Information System (INIS)

    Alpatov, V. G.; Borzakov, S. B.; Davydov, A. V.; Isaev, Yu. N.; Kartashov, G. R.; Korotkov, M. M.; Nazarov, V. M.; Pavlov, S. S.; Peresedov, V. F.; Rad'ko, V. E.; Samoylov, V. M.; Chinaeva, V. P.

    1997-01-01

    The cross sections for the excitation of long-lived isomers of 107,109 Ag nuclei are measured in the inelastic scattering of fast neutrons from the IBR-2 reactor of JINR (Dubna). The measurements are performed by means of comparison with the yield of the 103m Rh isomer, for which the excitation cross sections are known over a wide energy range for similar reactions induced by monochromatic neutrons. The measured cross sections proved to be σ( 107m Ag)=204±18 mb and σ( 109m Ag)=262±26 mb. These values are significantly smaller than the cross section for the excitation of the 103m Rh isomer. An analysis employing information about the arrangement of energy levels in Rh and Ag and about transitions between these levels, as well as data on the spectra of γ rays emitted in (n,n'γ) reactions, reveals that the distinction between the cross sections for the excitation of Rh and Ag isomers can be explained by the difference in the population of corresponding levels of Rh and Ag nuclei

  3. Analysis of neutron spectra and fluxes obtained with cold and thermal moderators at IBR-2 reactor: experimental and computer modeling studies at small-angle scattering YuMO setup

    International Nuclear Information System (INIS)

    Kuklin, A.I.; Rogov, A.D.; Gorshkova, Yu.E.; Kovalev, Yu.S.; Kutuzov, S.A.; Utrobin, P.K.; Rogachev, A.V.; Ivan'kov, O.I.; Solov'ev, D.V.; Gordelij, V.I.

    2011-01-01

    Results of experimental and computer modeling investigations of neutron spectra and fluxes obtained with cold and thermal moderators at the IBR-2 reactor (JINR, Dubna) are presented. The studies are done for small-angle neutron scattering (SANS) spectrometer YuMO (beamline number 4 of the IBR-2). The measurements of neutron spectra for two methane cold moderators are done for the standard configuration of the SANS instrument. The data from both moderators under different conditions of their operation are compared. The ratio of experimentally determined neutron fluxes of cold and thermal moderators at different wavelength is shown. Monte Carlo simulations are done to determine spectra for cold methane and thermal moderators. The results of the calculations of the ratio of neutron fluxes of cold and thermal moderators at different wavelength are demonstrated. In addition, the absorption of neutrons in the air gaps on the way from the moderator to the investigated sample is presented. SANS with the protein apoferritin was done in the case of cold methane as well as a thermal moderator and the data were compared. The perspectives for the use of the cold moderator for a SANS spectrometer at the IBR-2 are discussed. The advantages of the YuMO spectrometer with the thermal moderator with respect to the tested cold moderator are shown

  4. PREFACE: SANS-YuMO User Meeting at the Start-up of Scientific Experiments on the IBR-2M Reactor: Devoted to the 75th anniversary of Yu M Ostanevich's birth

    Science.gov (United States)

    Gordely, Valentin; Kuklin, Alexander; Balasoiu, Maria

    2012-03-01

    The Second International Workshop 'SANS-YuMO User Meeting at the Start-up of Scientific Experiments on the IBR-2M Reactor', devoted to the 75th anniversary of the birth of Professor Yu M Ostanevich (1936-1992), an outstanding neutron physicist and the founder of small-angle neutron scattering (field, group, and instrument) at JINR FLNPh, was held on 27-30 May at the Frank Laboratory of Neutron Physics. The first Workshop was held in October 2006. Research groups from different neutron centers, universities and research institutes across Europe presented more than 35 oral and poster presentations describing scientific and methodological results. Most of them were obtained with the help of the YuMO instrument before the IBR-2 shutdown in 2006. For the last four years the IBR-2 reactor has been shut down for refurbishment. At the end of 2010 the physical launch of the IBR-2M reactor was finally realized. Nowadays the small-angle neutron scattering (SANS) technique is applied to a wide range of scientific problems in condensed matter, soft condensed matter, biology and nanotechnology, and despite the fact that there are currently over 30 SANS instruments in operation worldwide at both reactor and spallation sources, the demand for beam-time is considerably higher than the time available. It must be remembered, however, that as the first SANS machine on a steady-state reactor was constructed at the Institute Laue Langevin, Grenoble, the first SANS instrument on a 'white' neutron pulsed beam was accomplished at the Joint Institute for Nuclear Research at the IBR-30 reactor, beamline N5. During the meeting Yu M Ostanevich's determinative and crucial contribution to the construction of spectrometers at the IBR-2 high-pulsed reactor was presented, as well as his contribution to the development of the time-of-flight (TOF) small-angle scattering technique, and a selection of other scientific areas. His leadership and outstanding scientific achievements in applications of the

  5. Measuring and acquisition unit of the polarized neutron spectrometer SPN-1; Izmeritel`no0nakopitel`nyj modul` spektrometra na polyarizovannykh nejtronakh SPI-1

    Energy Technology Data Exchange (ETDEWEB)

    Zhuravlev, V V; Korneev, D A; Litvinenko, E I; Lyapin, D I

    1996-12-31

    SPN-1 polarized neutron time-of-flight spectrometer operates on IBR-2 reactor in JINR LNF. It is used to investigate into micromagnetism in ferromagnetics and superconductors as well as to investigate into mono and multilayer magnetic and superconducting thin films. 14 refs.; 3 figs.

  6. Automation system for measurement of gamma-ray spectra of induced activity for multi-element high-volume neutron activation analysis at the IBR-2 reactor of FLNP at JINR

    International Nuclear Information System (INIS)

    Pavlov, S.S.; Dmitriev, A.Yu.; Chepurchenko, I.A.; Frontas'eva, M.V.

    2014-01-01

    The automation system for measurement of induced activity of gamma-ray spectra for multi-element high-volume neutron activation analysis (NAA) was designed, developed and implemented at the IBR-2 reactor. The system consists of three devices of automatic sample changers for three Canberra HPGe detector-based gamma spectrometry systems. Each sample changer consists of two-axis linear positioning module M202A by DriveSet (DriveSet.de) company and disk with 45 slots for containers with samples. Control of automatic sample changer is performed by the Xemo S360U controller by Systec (systec.de) company. Positioning accuracy can reach 0.1 mm. Special software performs automatic changing of samples and measurement of gamma spectra at constant interaction with the NAA database. The system is unique and can be recommended for other laboratories as one of the possible ways of the NAA integrated automation

  7. Analysis of arsenic and mercury content in human remains of the 16th and 17th centuries from Moscow Kremlin necropolises by neutron activation analysis at the IREN facility and the IBR-2 reactor FLNP JINR

    Science.gov (United States)

    Panova, T. D.; Dmitriev, A. Yu.; Borzakov, S. B.; Hramco, C.

    2018-01-01

    A neutron activation analysis (NAA) of three samples of human remains of the 16th and 17th centuries from the necropolises of the Moscow Kremlin has been carried out at FLNP JINR. The samples were irradiated at two facilities: the IREN source of resonance neutrons and the IBR-2 reactor. Spectra of the induced activity of the irradiated samples were measured by using the automatic measurement system developed at the Frank Laboratory of Neutron Physics (FLNP) of the Joint Institute for Nuclear Research (JINR). This system consists of a high-purity germanium detector with spectrometric electronics, a sample changer, and control software. Mass fraction of arsenic, mercury, and some other elements were calculated using two NAA methods—relative and absolute. The obtained values confirm the fact of acute mercury poisoning of Anastasia Romanovna, the first wife of Tsar Ivan Vasil'evich the Terrible, the first Russian Tsarina (died in 1560). High levels of mercury were detected in the bone remains of Tsarevich Ivan Ivanovich (died in 1581), the son of Tsar Ivan the Terrible, and Prince Mikhail Vasil'evich Skopin-Shuiskii (died in 1610). The results provide an opportunity to introduce into scientific circulation the exact values of mass fraction of mercury, arsenic, and other elements in the samples taken from the burials of the Russian historical figures of the second half of 16th-early 17th century.

  8. Qualitative and quantitative analysis of arsenic and mercury in human remains of the XVI-XVII centuries from the Moscow Kremlin necropolises by neutron activation analysis at the IREN facility and the IBR-2 reactor of FLNP, JINR

    International Nuclear Information System (INIS)

    Panova, T.D.; Dmitriev, A.Yu.; Borzakov, S.B.; Khramko, K.

    2017-01-01

    The neutron activation analysis (NAA) of three samples of human remains of the XVI-XVII centuries from the necropolises of the Moscow Kremlin has been carried out at FLNP JINR. The samples were irradiated at two facilities: at the IREN source of resonance neutrons and at the IBR-2 reactor. Spectra of induced activity of the irradiated samples were measured by using the automatic measurement system developed at FLNP JINR. This system consists of a high-purity germanium detector with spectrometric electronics, a sample changer, and a control software. Mass fractions of arsenic, mercury and other elements were calculated by relative and absolute NAA methods. The obtained values confirmed the fact of an acute mercury poisoning of the first wife of Tsar Ivan Vasilievich the Terrible - Tsarina Anastasia Romanovna. Increased mercury content was detected in the bone remains of the son of Tsar Ivan the Terrible, Tsarevich Ivan Ivanovich, and Prince M. V. Skopin-Shuisky. The obtained results allow us to introduce into scientific circulation the exact values of mass fraction of mercury, arsenic and some other elements in the samples from the graves of Russian historical figures of the second half of XVI - early XVII centuries. [ru

  9. MASURCA, a Fast-Neutron Critical Mock-Up: Operation and Uses; MASURCA. Maquette Critique a Neutrons Rapides. Description Fonctionnelle et Obiectifs; ''MAZURKA'' - kriticheskaya model' na bystrykh nejtronakh. funktsional'noe opisanie i tseli; Descripcion Funcional y Objetivos de la Maqueta Critica de Neutrones Rapidos 'MASURCA '

    Energy Technology Data Exchange (ETDEWEB)

    Schmitt, A. P.; Storrer, F.; Vendryes, G. [Association CEA-EURATOM, Cadarache (France); Tavernier, G.; Van Dievoet, J. [Societe Belgo-Nucleaire, Bruxelles (Belgium)

    1964-02-15

    Under the EURATOMCEA Association project a fast-neutron critical mock-up, Masurca, is now being built at the Cadarache Nuclear Research Centre. The main purpose of this extremely versatile facility is the study of non-moderated, plutonium critical assemblies of large volume and hence having a relatively soft neutron spectrum. The paper explains what these studies are for. The facility must satisfy certain conditions and, in essence, combine great versatility with almost absolute operational safety. The safety problem was dealt with by: (1) Seeking inherent safety: with simulated fuel elements it was possible to obtain (a) a negative reactivity coefficient from the cumulative longitudinal expansion of these elements: (b) a negative Doppler coefficient; (2) Using a set of shim-safety rods which can be placed in a square lattice with spacings of about 30cm; (3) A pressure vessel, containing reserves of argon in case of fire: and (4) Strict administrative supervision. A U-Pu-Fe metallic alloy being chosen as the basic element in the fuel simulation, provision for cooling large-volume critical assemblies must be incorporated in the facility. Sodium, the coolant used in simulated reactors, will be represented by sodium strips clad in stainless steel. The facility is designed as a vertical single-block unit in view of the maximum volume of the cores to be simulated (about 5000 1). The simulated elements are shaped like a right prism with a square base (except in the case of fuel elements which have a circular base) with an outer side (or diameter) of 12.7 mm and a height of 102 mm. They are placed in tubes having an over- all length of about 4 m and square sections whose outer side is 10.6 mm. These tubes are placed side by side and suspended. Smaller tubes can be placed in the central area of the suspension plate so that smaller cores can be made. A special heating loop can also be placed in the central part of the facility to measure the Doppler coefficient. The paper describes how the facility works. Reference is made to the possibility of simulating fast reactor oxide cores (by using ferrous oxide elements to introduce oxygen) and carbide cores (by using graphite elements). The paper also discusses the mixed loading technique which will have to be used in view of the amounts of plutonium available for such experiments during the present decade, and the techniques which will be used to determine the basic neutron parameters. The place of this critical mock-up in the general basic physics research of fast neutron reactor development is indicated: the experimental means involved include a Harmonie reactor source, to serve in developing measuring techniques and providing data for exponential experiments, and accelerators serving as static and dynamic neutron sources for subcritical experiments with fast neutrons. (author) [French] Dans le cadre de l'Association EURATOM-CEA, on construit actuellement au Centre d'etudes nucleaires de Cadarache une maquette critique a neutrons rapides appelee 'Masurca'. Cette machine d'une grande souplesse est essentiellement destinee a faire des etudes sur des assemblages critique, non ralentis, au plutonium, de grand volume ayant donc un spectre neutronique relativement mou. Les buts de ces etudes sont developpes dans le memoire. Pour mener a bien ces travaux, une machine de ce genre doit satisfaire a un certain nombre de conditions: essentiellement, elle doit associer a une grande souplesse d'utilisation une securite de fonctionnement quasi absolue. Ce probleme de securite a ete resolu par: 1. Une recherche de securite intrinseque, les elements de simulation du combustible permettant d'obtenir a) un coefficient de reactivite negatif du a la dilatation longitudinale cumulative de ces elements et b) un coefficient Doppler negatif; 2. L'utilisation d'un jeu de barres de controle de securite et de compensation. Ces barres peuvent se placer suivant un reseau carre de 30 cm de pas environ; 3. Uneenceinte etanche dans laquelle se trouve une reserve d'argon contre incendie; 4. Un controle administratif strict. Le choix d'un alliage metallique U-Pu-Fe, comme element de base de la simulation du combustible, impose de prevoir un refroidissement des assemblages critiques de grand volume construit dans la machine. Le sodium, fluide de refroidissement des reacteurs a simuler, sera represente par des reglettes de sodium gainees d'acier inoxydable. La conception de cette machine est du type vertical- monobloc. Les raisons qui ont conduit a ce choix sont liees au volume maximum des coeurs qu'il est prevu de simuler (de l'ordre de 5000 1). Les elements de simulation ont la forme d'un prisme droit a base carree (sauf pour les elements combustibles qui ont une base circulaire) de 12,7 mm de cote (ou de diametre) exterieur et de 102 mm de hauteur. Il sont places dans des tubes de section carree de 106 mm de cote exterieur et de l'ordre de 4 m de longueur hors tout. Ces tubes sont places cote a cote et suspendus. La region centrale de la plaque de suspension peut accepter de plus petits tubes pour permettre de monter des coeurs de petite dimension. Une boucle speciale chauffante peut egalement se placer dans la partie centrale de la machine, afin de pouvoir mesurer le coefficient Doppler. Le memoire presente une description fonctionnelle de la machine. On mentionne la possibilite de realiser la simulation de coeurs de reacteurs rapides a oxydes (a l'aide d'elements d'oxyde de fer pour introduire l'oxygene) et a carbures (a l'aide d'elements en graphite). On discute la technique de chargements mixtes qu'il faudra employer compte tenu de l'inventaire en plutonium disponible pour de telles experiences dans la presente decennie, et les techniques qui seront utilisees pour la determination des parametres neutroniques fondamentaux. Enfin, on indique la place qu'occupe cette maquette critique dans l'ensemble des recherches de physique de base liees au developpement des reacteurs a neutrons rapides. En particulier les moyens experimentaux mis en oeuvre comprennent un reacteur source ' Harmonie ' destine a la mise au point des techniques de mesure et a l'alimentation d'experiences exponentielles, et des accelerateurs fonctionnant comme source de neutrons statique et dynamique pour alimenter des experiences sous-critiques a neutrons rapides. (author) [Spanish] El EURATOM y el Commissariat a l'energie atomique estan construyendo actualmente en el Centre d'etudes nucleaires de Cadarache, una maqueta critica de neutrones rapidos denominada <>. Esta instalacion, de gran flexibilidad de aplicacion se destina esencialmente a la realizacion de estudios sobre conjuntos criticos de plutonio, de gran volumen, sin moderador, cuyo espectro neutronico es, pues, relativamente blando. Los autores exponen en la memoria el proposito de taies estudios. A fin de asegurar su exito, la instalacion debe reunir ciertas condiciones: en esencia, ademas de su gran capacidad de adaptacion, debe ofrecer una seguridad de funcionamiento practicamente absoluta. Este problema de la seguridad se resolvio por los siguientes medios: 1. Estudio de las condiciones de seguridad inulhseca; los elementos de simulacion del combustible permiten obtener a) un coeficiente de reactividad negativo, debido a la dilatacion longitudinal acumulativa de estos elementos y b) un coeficiente Doppler negativo. 2. Empleo de un juego de barras de control de seguridad y de compensacion. Estas barras pueden colocarse en forma de reticulado cuadrado con un espaciamiento de unos 30 cm. 3. Un iecinto hermetico que contiene una reserva de argon contra incendios. 4. Un estricto control administrative. La adopcion de una aleacion metalica U-Pu-Fe para la simulacion del combustible obliga a asegurar la refrigeiacion de los conjuntos criticos de gran volumen construidos en la instalacion. El sodio, llquido refrigerante de los reactores simulados, estara representado por varillas de sodio revestidas de acero inoxidable. El concepto de esta instalacion se ajusta- al tipo monobloque vertical. Las razones que decidieron esta eleccion guatdan lelacion con el volumen maximo de los cuerpos que se proyecta simular (que es del orden de los 5000 l). Los elementos simulados adoptan la forma de un prisma recto de base cuadrada (salvo los elementos combustibles, que tienen base circular), de 12,7 mm de lado(o de diametro), exteriormente, por 102 mm de altura. Estan colocados dentro de tubos de seccion cuadrada de 106 mm de lado, de una longitud de unos 4 m de punta a punta. Estos tubos estan yuxtapuestos y suspendidos de una placa. La region central de esta placa de suspension admite tambien tubos mas pequeflos, a fin de facilitar la instalacion de cuerpos de menor tamaflo. Asimismo, se puede montar en el centro de la instalacion un circuito especial de calentamiento, a fin de medir el coeficiente Doppler. La memoria presenta una descripcion funcional de la instalacion. Se alude a la posibilidad de realizar una simulacion de cuerpos de reactores rapidos a base de oxido (mediante elementos de oxido de hierro para introducir el oxfgeno) y de carburos (mediante elementos de grafito). Se describe la tecnica de las cargas mixt as que sera menester aplicar, habida cuenta de las reservas de plutonio disponibles para estos experimentos en el corriente decenio y las tecnicas que se utilizaran para determinar los parametras neutranicos esenciales. Por oltimo, los autores indican el lugar que ocupa esta maqueta critica en el marco de las investigaciones de fisica fundamental relacionadas con el desarrollo de los reactores de neutrones rapidos. En particular, entre los roedios experimentales utilizados, figura un reactor-fuente Uamado 'Harmonie', destinado al perfeccionamiento de las tecnicas de medicion y a servir como fuente en experimentos exponenciales, asi como unos aceleradores que actdan como fuentes neutronicas estaticas y dinamicas para llevar a cabo experimentos subcriticos con neutrones rapidos. (author) [Russian] V nastojashhee vremja v Centre jadernyh issledovanij Kadarash v ramkah Associacii Evratom -KAJe konstruiruetsja kriticheskij maket na bystryh nejtro- nah pod nazvaniem {sup M}azurka{sup .} Jeta ustanovka obladaet bol'shimi vozmozhnostjami dlja pro- vedenija jeksperimentov i prednaznachena glavnym obrazom dlja provedenija issledovanij na krupnyh plutonievyh kriticheskih sborkah bez zamedlitelej s otnositel'no podvizhnym nej- tronnym spektrom. Izlagajutsja celi issledovanij, dlja osushhestvlenija kotoryh podobnaja ustanovka dolzhna otvechat' opredelennym uslovijam. Prezhde vsego ona dolzhna imet' bol'shuju gibkost' v ispol'zovanii i obespechivat' pochti absoljutnuju bezopasnost' v rabote. Problema bezopasnosti byla reshena putem: 1 .Issledovanija prisushhej ustanovke bezopasnosti; jelementy, imitirujushhie toplivo, pozvolili poluchit': a) kojefficient otricatel'noj reaktivnosti v rezul'tate kumu- ljativnogo prodol'nogo rasshirenija jetih jelementov; b) otricatel'nyj kojefficient Dopplera. 2 .Ispol'zovanija puchka avarijnyh upravljajushhih sterzhnej i kompensirujushhih sterzhnej; jeti sterzhni mogut razmeshhat'sja na reshetke s kvadratom 30 sm. 3.Primenenija germeticheskoj kamery s argonom na sluchaj pozhara. 4 . Strogogo administrativnogo kontrolja. Vybor metallicheskogo splava uran -plutonij -zhelezo v kachestve osnovnogo jelementa imitirovanija topliva zastavljaet predusmatrivat' ohlazhdenie krupnyh kriticheskih sborok v ustanovke. Natrij v kachestve zhidkogo ohladitelja dlja modeliruemyh reaktorov predstavlen natrie- vymi palochkami v obolochke iz nerzhavejushhej stali. Jeta ustanovka predstavljaet soboj vertikal'no-monoblokovyj tip. Takoj vybor ob{sup -} jasnjaetsja stremleniem poluchit' maksimal'nyj ob{sup e}m aktivnyh zon, kotoryj bylo predusmot- reno modelirovat' (porjadka 5000 l). Imitirujushhie jelementy imejut formu prjamoj prizmy s kvadratnym osnovaniem (krome toplivnyh jelementov s krugovoj osnovoj) s vneshnej storonoj (ili diametrom) 12,7 mm i vysotoj 102 mm. Oni razmeshheny v trubah kvadratnogo sechenija s vneshnej storonoj 106 mm i dlinoj porjadka 4 m. Jeti truby nahodjatsja v pod- veshennom sostojanii rjadom drug s drugom. Central'naja chast' podveshennoj plity mozhet prinimat' men'shie truby, chto pozvoljaet sozdavat' aktivnye zony nebol'shih razmerov. Special'nyj podogretyj kontur takzhe mozhet peremeshhat'sja v central'noj chasti ustanovki, chto daet vozmozhnost' izmerjat' kojefficient Dopplera. V doklade daetsja funkcional'noe opisanie ustanovki. Ukazyvaetsja na vozmozhnost' osushhestvlenija modelirovanija aktivnyh zon bystryh reaktorov na okislah (s pomoshh'ju jelementov iz okisi zheleza dlja vvedenija kisloroda) i na karbidah (s pomoshh'ju grafitovyh jele- mentov). Obsuzhdaetsja metod smeshannyh zagruzok, ko.toryj neobhodimo budet primenjat' vvidu opredelennogo kolichestva plutonija, ispol'zuemogo v takih opytah v nastojashhem desja- tiletii, i metodov, kotorye budut primenjat'sja dlja opredelenija osnovnyh nejtronnyh pa- rametrov. V zakljuchenie ukazyvaetsja mesto, kotoroe zanimaet jetot kriticheskij maket sredi os- novnyh fizicheskih issledovanij, svjazannyh s razrabotkoj reaktorov na bystryh nejtronah. V chastnosti, ispol'zovannye jeksperimental'nye sredstva vkljuchali reaktor-istochnik ''Garmonija'', prednaznachennyj dlja razrabotki,metodov izmerenija i dlja obespechenija jeksponenci- al'nyh opytov, a takzhe uskoriteli v kachestve istochnika staticheskih i dinamicheskih nejtronov dlja obespechenija podkriticheskih opytov na bystryh nejtronah. (author)

  10. The Control of Fast Reactors: Current Methods and Future Prospects; Controle des Reacteurs a Neutrons Rapides. Methodes Actuelles et Perspectives d'Avenir; Upravlenie reaktorami na bystrykh nejtronakh. sushchestvuyushchie metody i dal'nejshie perspektivy; Control de Reactores Rapidos: Metodos Actuales y Perspectivas

    Energy Technology Data Exchange (ETDEWEB)

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

    1964-06-15

    The practical aspects of providing adequate reactivity for the control of fast reactors which differ significantly from those used to control thermal-neutron systems are discussed. These differences result primarily from the rather small fast-neutron cross-sections. There are no strong poisons in a fast-neutron system. As a result, the strong thermal-reactor fission-product poisons (e.g. Xe and Sm) require significantly less reactivity override than the reactivity loss from destruction, by fission and capture, of fissionable material. Because the fast-spectrum atomic cross-sections are relatively small compared with their thermal counterparts, the atomic density of the material plays an important role in the choice of control materials. The current generation of fast-neutron reactor control mechanisms is described. These tend to exploit neutron leakage control, where applicable. If leakage control is not feasible, control by moving of core material has found considerable acceptance. Limited absorber control is also being used. None of these methods has significant advantages for application to the large conceptual central-station power-breeder reactor system unless the internal (core) breeding ratio is very high. Considerable ingenuity will have to be applied for use of either absorber or spectral-shift control methods without seriously affecting the desired and often required neutron economy. Exploratory results pertaining to the advanced systems are cited. The reactivity for control is dictated by reactor shutdown requirements, the reactor fuel cycle (excess reactivity) and, to a lesser extent, the dominant feedbacks. The excess reactivity requirements can be quite well specified in terms of a given fuel cycle but may vary considerably for several similar systems operating on different fuel cycles. The required shutdown reactivity, may be almost arbitrarily specified beyond certain limits. However, there are certain philosophical implications which prevail regarding the specification of this parameter. These considerations are discussed in terms of control reactivity in existing fast reactors as opposed to the amount that is really required for fast power-breeder reactor operation. Typical power- and temperature-dependent feedback parameters are cited for determination of their influence upon the control reactivity requirements. The methods used to predict the reactivity worth of control mechanisms have evolved from crude estimates to quite reliable calculations which can be confirmed by experimental data from critical assemblies. Experimental results and currently reliable analytical techniques are described. Critical experiments for the current generation of fast reactors included many investigations pertaining to the reactivity worth of their control mechanisms as well as peripheral experiments for larger-core-volume advanced systems. Exploratory analytical studies, which indicate that detailed experimental mockup investigations may not be required in the future, are cited. (author) [French] L'auteur examine dans ce memoire les aspects pratiques du probleme qui consiste a fournir une reactivite suffisante pour le controle des reacteurs a neutrons rapides; ce probleme differe dans une grande mesure de celui du controle des reacteurs a neutrons thenniques. Ces differences sont dues en premier lieu au fait que les sections efficaces d'absorption des neutrons rapides sont assez faibles. Il n'existe pas de poisons forts dans un reacteur a neutrons rapides. En consequence, les poisons forts que sont certains produits de fission dans un reacteur thermique (par exemple Xe et Sm) exigent un exces de reactivite beaucoup moins important que n'en exige la perte de reactivite due a la destruction de produit fissile par fission et capture. Comme les sections efficaces pour les neutrons rapides sont relativement petites comparees aux valeurs correspondantes pour les neutrons thermiques, la densite atomique du materiau joue un role important dans le choix des materiaux absorbants. L'auteur decrit les modeles actuels de mecanismes de controle d'un reacteur a neutrons rapides. Ceux-ci ont tendance a tirer parti, la ou cela est possible, du principe du controle des fuites de neutrons. La ou il n'est pas possible d'appliquer ce principe, on a frequemment recours au controle par deplacement de matieres du coeur. On a egalement recours dans une certaine mesure au controle par absorbant. Aucune de ces methodes ne presente d'avantages notables lorsqu'elle est appliquee au reacteur surgenerateur d'une centrale, a moins que le rapport de conversion dans le coeur ne soit tres eleve. Il faudra deployer beaucoup d'ingeniosite pour trouver le moyen d'utiliser les methodes de controle par absorbant ou par modification du spectre sans affecter gravement l'economie des neutrons souhaitee et souvent necessaire. L'auteur mentionne les resultats d'etudes portant sur les systemes les plus perfectionnes. La reactivite qu'il faut donner aux barres de controle est determinee par la reactivite necessaire pour l'arret brusque du reacteur, le cycle du combustible (exces de reactivite) et dans une mesure mouns grande, les effets des facteurs dominants. On peut fixer tres exactement l'exces de reactivite pour un cycle de combustible donne, mais cet exces peut varier considerablement pouf des reacteurs similaires, s'ils fonctionnent avec des cycles de combustible differents. On peut, dans certaines limites, fixer presque arbitrairement la reactivite necessaire pour l'arret brusque. Cependant, certaines considerations militent en faveur d'une determination precise de ce parametre. L'auteur examine la question sous tous ces aspects en comparant la reactivite des barres de controle dans les reacteurs a neutrons rapides actuels et la quantite de reactivite dont on a reellement besoin pour le fonctionnement d'un reacteur surgenerateur a neutrons rapides.. P cite les parametres typiques dependant de la puissance et de la temperature pour determiner leurs effets sur la quantite de reactivite qu'il faut donner aux barres de controle. Les methodes utilisees pour la prevision de l'efficacite des mecanismes de controle ont evolue: au debut, il s'agissait d'evaluations approximatives; on fait maintenant des calculs tout a fait surs que peuvent confirmer les donnees experimentales obtenues grace aux assemblages critiques. L'auteur indique dans ce memoire certains resultats experimentaux et expose les methodes analytiques sflres que l'on emploie couramment. Les experiences critiques portant sur la generation actuelle de reacteurs a neutrons rapides ont comporte de nombreuses recherches concernant l'efficacite de leur mecanisme de commande, ainsi que des experiences a la peripherie du coeur pour l'etude de reacteurs perfectionnes ayant un coeur d'un plus grand volume. L'auteur mentionne des etudes analytiques preliminaires qui montrent qu'il ne faudra peut-etre pas proceder dans l'avenir a des recherches experimentales detaillees sur maquette. (author) [Spanish] El autor examina los aspectos practicos del problema consistente en obtener una reactividad suficiente para el control de los reactores de neutrones rapidos, control que es muy diferente del utilizado en los sistemas de neutrones termicos. Las diferencias se deben en primer lugar a los valores relativamente pequenos de las secciones eficaces para los neutrones rapidos. En un sistema de neutrones rapidos no hay venenos fuertes. Como consecuencia, los fuertes venenos de fision (por ejemplo, el Xe y el Sm) en los reactores termicos exigen un exceso de reactividad mucho menor que la perdida de reactividad causada por la destruccion del material fisionable por fision y captura. Como las secciones eficaces del espectro de neutrones rapidos son relativamente pequenas comparadas con las correspondientes a los neutrones termicos, la densidad atomica del material desempena un papel importante al elegir los materiales de las barras de control. El autor examina los actuales mecanismos de control de los reactores de neutrones rapidos. En la medida de lo posible aprovechan el control por medio de fugas neutronicas. Si este metodo no es aplicable se suele recurrir al control por desplazamiento de los materiales del cuerpo. Igualmente se recurre a un control limitado utilizando un absorbente. Ninguno de estos metodos presenta ventajas considerables cuando se aplica a los'grandes reactores de potencia regeneradores, a menos que la razon interna de regeneracion (del cuerpo) sea muy elevada. Se requerira mucha habilidad para utilizar metodos de control basados en el empleo de un absorbente o en el desplazamiento espectral sin afectar en grado apreciable la economia neutronica deseada y a menudo necesaria. El autor cita algunos resultados preliminares obtenidos con sistemas perfeccionados. La reactividad de control viene determinada por los requisitos relativos a la parada del reactor, al ciclo del combustible (exceso de reactividad) y, en menor medida, por la realimentacion dominante. Pueden especificarse perfectamente los requisitos relativos al exceso de reactividad para un ciclo de combustible determinado, pero esos requisitos varian de modo considerable en otros sistemas similares que funcionen con distintos ciclos de combustible. A partir de ciertos limites, pueden fijarse casi arbitrariamente les requisitos relativos al exceso de reactividad. Sin embargo, existen algunas consideraciones generales que rigen la determinacion de este parametro. Se tienen en cuenta dichas consideraciones al examinar la reactividad de control en los actuales reactores de neutrones rapidos comparandola a la cantidad realmente necesaria para el funcionamiento de reactores de potencia regeneradores y neutrones rapidos. El autor cita parametros tipicos de potencia y de realimentacion en funcion de la temperatura a fin de determinar su influencia en los requisitos relativos a la reactividad de control. Los metodos utilizados para predecir la efectividad de los mecanismos de control han evolucionado desde evaluaciones poco precisas hasta calculos muy fidedignos confirmados experimentalmente en conjuntos criticos. El autor describe los resultados experimentales y las tecnicas analiticas, que suelen ser seguras. Los experimentos criticos que precedieron la construccion de los actuales modelos de reactores de neutrones rapidos comprendieron muchas investigaciones sobre la efectividad de sus mecanismos de control y experimentos marginales para sistemas perfeccionados en los que el cuerpo tiene un volumen mayor. El autor cita algunos estudios analiticos provisionales de los que se puede deducir que no habra necesidad de efectuar en lo sucesivo investigaciones experimentales detalladas en maquetas. (author) [Russian] Obsuzhdajutsja prakticheskie aspekty obespechenija sootvetstvujushhej reaktivnosti dlja upravlenija reaktorami na bystryh nejtronah, kotorye sushhestvenno otlichajutsja ot analogichnyh aspektov pri osushhestvlenii kontrolja sistem teplovyh nejtronov. Jeti razlichija vyzvany glavnym obrazom blagodarja nebol'shim sechenijam na bystryh nejtronah. V sistemah na bystryh nejtronah otsutstvujut sil'nye poglotiteli nejtronov. V rezul'tate jetogo takie sil'nye poglotiteli nejtronov v teplovyh reaktorah, kak produkty raspada (naprimer He i Zt)trebujut znachitel'no men'she reaktivnosti na ih kompensaciju, chem poterja reaktivnosti, vyzvannaja deleniem i zahvatom rasshhepljajushhihsja materialov. Poskol'ku atomnye sechenija bystrogo spektra dovol'no maly po sravneniju s sechenijami dlja teplovyh nejtronov atomnaja plotnost' materiala igraet vazhnuju rol' pri vybore materialov dlja regulirujushhih sterzhnej. Opisyvajutsja sushhestvujushhie tipy kontrol'nyh mehanizmov reaktorov na bystryh nejtronah. Jeti sposoby napravleny na vozmozhnost' ispol'zovanija, tam, gde jeto priemlemo,, kontrolja za utechkoj nejtronov. Kogda takoj kontrol' prakticheski neosushhestvim, to pri menjaetsja kontrol' s pomoshh'ju peredvizhenija materialov aktivnoj zon'/. Primenjaetsja takzhe ogranichennyj kontrol' s pomoshh'ju poglotitelej. Odnako ni odin iz jetih metodov ne daet sushhestvennogo preimushhestva dlja togo, chtoby ego primenjat' k jenergeticheskim reaktoram- razmnozhiteljam krupnyh central'nyh atomnyh stancij, esli vnutrennij (v aktivnoj zone) kojefficient vosproizvodstva ne javljaetsja ochen' vysokim. Dolzhna byt' projavlena bol'shaja izobretatel'nost' dlja togo, cht.oby ispol'zovat' libo metod poglotitelja, libo metod regulirovki spektral'nogo smeshhenija, ne okazav ser'eznogo vlijanija na zhelaemuju i ..chasto trebuemuju jekonomiju nejtronov. Privodjatsja rezul'taty issledovanij, imejushhie-otnoshenie k usovershenstvovannym sistemam. Reaktivnost', neobhodimaja dlja upravlenija reaktorom, opredeljaetsja potrebnostjami ostanovki reaktora, toplivnym ciklom reaktora (izbytochnaja reaktivnost') i v gorazdo men'shej stepeni dominirujushhej obratnoj svjaz'ju. Trebovanija k izbytochnoj reaktivnosti, mogut byt' s uspehom opredeleny dannym toplivnym ciklom, odnako mogut znachitel'no var'irovat'sja dlja celogo rjada analogichnyh sistem, rabotajushhih na razlichnyh toplivnyh ciklah. Neobhodimuju ostatochnuju reaktivnost' mozhno ustanovit' pochti proizvol'no vyshe opredelennoj predel'noj velichiny. Odnako imeetsja celyj rjad filosofskih momentov, kotorye kasajutsja specifikacii jetogo parametra. Jeti soobrazhenija obsuzhdajutsja s tochki zrenija regulirovki reaktivnosti v sushhestvujushhih reaktorah na bystryh nejtronah, poskol'ku jeto svjazano s kolichestvom, kotoroe dejstvitel'no trebuetsja dlja jekspluatacii jenergeticheskih reaktorov-razmnozhitelej. Privodjatsja tipichnye parametry moshhnosti i parametry temperatury, zavisjashhej ot obratnoj svjazi dlja togo, chtoby opredelit' ih vlijanie na trebovanija po upravleniju reaktivnost'ju . Metody, ispol'zuemye dlja togo, chtoby predopredelit' reaktivnost' sootvetstvujushhih kontrol'nyh mehanizmov, polucheny na osnove grubyh podschetov, a takzhe s pomoshh'ju vpolne nadezhnyh vychislenij, kotorye mogut byt' podtverzhdeny jeksperimental'nymi dannymi, poluchennymi na kriticheskih sborkah. Opisyvajutsja jeksperimental'nye rezul'taty i nedavno ispol'zovannye tochnye analiticheskie metody. Kriticheskie jeksperimenty dlja sushhestvujushhej gruppy reaktorov na bystryh nejtronah vkljuchajut mnogo issledovanij, otnosjashhihsja k reaktivnoj sposobnosti ih kontrol'nyh mehanizmov', a takzhe pereferijnyh jeksperimentov dlja usovershenstvovannyh sistem s gorazdo bol'shim ob{sup e}mom aktivnoj zony. Privodjatsja issledovatel'skie analiticheskie raboty, kotorye ukazyvajut na to, chto v budushhem, vozmozhno, ne potrebuetsja provedenie podrobnyh issledovanij na jeksperimental'nyh modeljah v natural'nuju velichinu. (author)

  11. Some physics aspects of cermet and ceramic fast systems; Quelques aspects de la physique des reacteurs a neutrons rapides utilisant des cermets et des ceramiques comme combustibles; Nekotorye fizicheskie aspekty kermetnykh i keramicheskikh sistem na bystrykh nejtronakh; Algunos aspectos fisicos de los sistemas rapidos a base de combustibles cermet y ceramicos

    Energy Technology Data Exchange (ETDEWEB)

    Codd, J; James, M F; Mann, J E [United Kingdom Atomic Energy Authority, Reactor Group (United Kingdom)

    1962-03-15

    The characteristics of a system using an iron-based oxide cermet as fuel material are discussed. A transport theory investigation to develop methods of predicting the effect of core heterogeneity on reactivity and flux distribution is described. Some preliminary calculations are also given of resonance self-shielding and Doppler temperature effects in a cermet system. (author) [French] Les auteurs etudient les caracteristique s d'un reacteur utilisant comme combustible un cermet d'oxydes a armature de fer. Ils exposent une application de la theorie du transport a la mise au point des methodes permettant de prevoir l'effet de l'heterogeneite du coeur sur la reactivite et sur la distribution du flux. Ils donnent egalement quelques calculs preliminaires d'effets d'autoprotection due a la resonance et d'effet Doppler du a la chaleur dans un reacteur utilisant un cermet. (author) [Spanish] La memoria discute las caracteristicas de un sistema que emplea como combustible un oxido tipo cermet a base de hierro. Describe una investigacion de la teoria de transporte con miras a desarrollar metodos para evaluar el efecto de la heterogeneidad del cuerpo sobre la reactividad y la distribucion de flujo. Tambien da algunos calculos preliminares de los efectos del autoblindaje por resonancia y de la temperatura de Doppler en un sistema de tipo cermet. (author) [Russian] Obsuzhdayutsya kharakteristiki sistemy, ispol'zuyushchej v kachestve toplivnogo materiala oksidnye kermety, razrabotannye na osnove zheleza. Opisyvaetsya issledovanie teorii perenosa, chtoby razvit' metody predskazaniya vliyaniya geterogennosti aktivnoj zony na reaktivnost' i raspredelenie potoka. Dayutsya takzhe nekotorye predvaritel'nye raschety ehffektov rezonansnoj samozashchity i temperaturnogo ehffekta Dopplera v kermetnoj sisteme. (author)

  12. Measurement of resonance parameters of cross-sections affecting fast-neutron propagation in various media; Mesure des parametres de resonance de sections efficaces lies a la propagation des neutrons dans differents milieux; Izmerenie parametrov rezonansnoj struktury sechenij, vliyayushchikh na rasprostranenie bystrykh nejtronov v sredakh; Medicion de los parametros de resonancia de las secciones eficaces que afectan a la propagacion de los neutrones rapidos en distintos medios

    Energy Technology Data Exchange (ETDEWEB)

    Nikolaev, M N; Filippov, V V; Bondarenko, I I [Academy of Sciences, Moscow, Union of Soviet Socialist Republics (Russian Federation)

    1962-03-15

    propagacion de los neutrones en la materia abarca desde algunas decenas de kiloelectron-voltios , para los nucleos pesados, hasta unos cuantos mega-electron-voltios, para los nucleos intermedios. Para poder tener en cuenta los efectos de resonancia en el calculo de los parametros de los grupos, es indispensable conocer no solo las secciones eficaces medias correspondientes a las reacciones de los neutrones con la materia, sino tambien algunas magnitudes tales como (1/{Sigma}{sub t}), (1/{Sigma}{sub t}{sup 2}) etc. - los corchetes indican que se toman valores promedios de los grupos energeticos. La informacion de que se dispone actualement acerca de los parametros de resonancia en el terreno de los neutrones rapidos no permite calcular las magnitudes mencionadas con la exactitud necesaria. Por tal razon interesa medir directamente (1/{Sigma}{sub t}), (1/{Sigma}{sub t}{sup 2}) y otros valores analogos. Los autores presentan los resultados de las mediciones de una serie de parametros tales como ({Sigma}{sub t}), ({Sigma}{sub t}{sup 2}), (1/{Sigma}{sub t}), (1/{Sigma}{sub t}{sup 2}), (1/{Sigma}{sub t}{sup 3}), etc. que caracterizan la estructura de las secciones eficaces de una serie de nucleos intermedios para neutrones de energia comprendida entre 300 keV y 3 MeV. Dichos valores se dedujeron analizando las curvas de paso a traves de la materia, obtenidas con una geometria favorable, hasta un valor limite de 10{sup -2}, aproximadamente . Los datos obtenidos demuestran que los efectos de resonancia ejercen una notable influencia sobre las caracteristicas de la difusion en la materia. (author) [Russian] Pri sostavlenii sistem mnogogruppovykh konstant dlya rascheta reaktorov na bystrykh i promezhutochnykh nejtronakh vo mnogikh sluchayakh neobkhodimo uchityvat' ehffekty samoehkranirovki , svyazannye s rezonansnoj strukturoj sechenij. EHnergeticheskaya oblast', v kotoroj rezonansnaya struktura okazyvaet sushchestvennoe vliyanie na rasprostranenie nejtronov v veshchestve

  13. Solid methane cold moderator for the IBR-2 reactor

    International Nuclear Information System (INIS)

    Beliakov, A. A.; Tretiakov, I. T.; Shabalin, E. P.; Golikov, V. V.; Luschivkov, V I.

    1997-09-01

    The paper describes the research and design work carried out since 1986 at the Frank Laboratory of Neutron Physics of the Joint Institute for Nuclear Research in Dubna to create a cryogenic moderator for the IBR-22 reactor using solid methane as a moderating substance.

  14. Controllable Pulse Frequency and Width System for Pulsing and Modulating Fast-Neutron Core Assemblies; Systeme a Frequence et Largeur d'Impulsions Ajustables Permettant la Pulsation et la Modulation de Milieux Multipliants Sous-Critiques a Neutrons Rapides; Sistema reguliruemykh chastoty i shiriny impul'sa, dayushaya impul's i modulyatsiyu razmnozhayushchikh sred na bystrykh nejtronakh; Sistema de Frecuencia y Amplitud de Impulso Ajustables, para Pulsar y Modular

    Energy Technology Data Exchange (ETDEWEB)

    Duquesne, M.; Lyon, F.; Schmitt, A. [Association Euratom-CEA-SECNR (France); Nucleaires de Cadarache, Centre d' Etudes [France; Gerbier, R. [Laboratoire des Accelerateurs - CEN de Grenoble (France); Nucleaires de Cadarache, Centre d' Etudes [France

    1965-10-15

    The authors describe a system for producing neutron bursts of independently controllable width and frequency. The rise and quenching times of these bursts are of the order of a few nanoseconds. The system is applied to high-frequency pulsed and modulated experiments. Rapidly quenched neutron bursts are produced by deflection of a pure deuteron beam which has previously been accelerated and sorted. Ions other than atomic deuterons are removed after acceleration in a 10 Degree-Sign magnetic sorting field. Consideration is also being given to a pre-acceleration sorting system offering the advantage of reduced bulk. The deuteron beam passes through the space between two plates where there is normally an electrostatic field which deflects the beam onto the surfaces of a diaphragm. Application of a very high potential pulse to the first plate cancels the field and thus brings the beam rapidly onto the neutron-producing target (beginning of the burst). The second plate then receives a pulse of the same type which restores the field and removes the beam from the target (end of the burst). The pulse rise time is of the order of 10 ns; disappearance from the target is faster. The duration of the burst can be controlled as required within reasonable limits by suitably increasing the interval between the two pulses. In some cases ion transit time in the plates is not negligible in relation to the duration of the step applied to them. In such cases, one of the plates is replaced by a travelling wave line to which the two pulses are applied successively. The potential pulse thus accompanies the deuteron cluster producing the burst. The burst times can thus be reduced below 4 ns. The first stages of the voltage step generators are transistorized. The output tubes are sealed-disc valves providing a 1500-V step in a few nanoseconds. A 50-MHz double tetrode is employed for pulses for the delay line. A detection system comprises a scintillator-photomultiplier device incorporating a coincidence-anticoincidence unit, a time analyser and a digital data recorder. (author) [French] Les auteurs on mis au point un systeme permettant la production de bouffees de neutrons de largeur et de frequence de recurrence reglables independamment. Les temps de montee et de descente de ces bouffees sont de l'ordre de quelques nanosecondes. Ce systeme est applique aux experiences puisees et modulees a haute frequence. Pour la production de boufees de neutrons a extinction rapide, on procede par deflection d'un faisceau de deuterons purs prealablement acceleres et tries. Les ions autres que les deuterons atomiques sont elimines apres acceleration dans un aimant de tri a 10 Degree-Sign . Les auteurs etudient egalement un systeme de triage avant acceleration qui aurait l'avantage d'un encombrement reduit. Le faisceau de deuterons passe dans l'espace compris entre deux plaques ou regne normalement un champ electrostatique qui deflechit le faisceau sur les parois d'un diaphragme. On applique a la premiere plaque une tres large impulsion de tension qui annule le champ, ce qui a pour effet d'amener rapidement le faisceau sur la cible neutronigene (debut de la bouffee). La deuxieme plaque recoit ensuite une impulsion du meme type qui retablit le champ et fait disparaitre le faisceau de la cible (fin de la bouffee). Le front de montee des impulsions est de l'ordre de 10 ns; le temps de disparition sur la cible est inferieur a cette derniere valeur. La duree de la bouffee peut etre reglee a volonte dans les limites raisonnables par un retard convenable de la seconde impulsion par rapport a la premiere. Dans certains cas, le temps de transit des ions dans les plaques n'est pas negligeable par rapport a la duree de {Gamma} echelon qui leur est applique. On remplace alors l'une des plaques par une ligne a onde progressive a laquelle sont appliquees successivement les deux impulsions. L'impulsion de tension accompagne ainsi le paquet de deuterons qui produit la bouffee. Les fronts de bouffee peuvent ainsi etre ramenes au -dessous de 4 ns. Les generateurs a echelon de tension sont transistorises dans leurs premiers etages. Les tubes de sortie sont des lampes a disque scelle permettant d'obtenir un echelon de 1500 V en quelques nanosecondes. Les auteurs utilisent une double tetrode de 50 MHz pour les impulsions destinees a la ligne de retard. Le systeme de detection utilise un dispositif scintillateur-photomultiplicateur dont la chafne comprend un ensemble coiencidence - anticoincidence, un analyseur de temps et un enregistreur numerique des informations. (author) [Spanish] Los autores han ideado un sistema que permite regular independientemente la amplitud y la frecuencia de los impulsos neutronicos. El tiempo de subida y bajada de los impulsos es del orden de algunos nanosegundos. Este sistema se emplea en los experimentos con neutrones pulsados y modulados de alta frecuencia. Para producir impulsos neutronicos de extincion rapida, se desvfa un haz de deuterones puros previamente acelerados y seleccionados. Los iones distintos de los deuterones se eliminan despues de la aceleracion en un iman selector de 10 Degree-Sign . Los autores estudian igualmente un sistema para efectuar la seleccion antes de la aceleracion que presenta la ventaja de ser de pequenas dimensiones. El haz de deuterones atraviesa el espacio comprendido entre dos placas en las que hay normalmente un campo electroestatico qiie desvfa el haz hacia las paredes de un diafragma. Se aplica a la primera placa un tortisimo impulso de tension que anula el campo, con lo que se dirige rapidamente el haz hacia el blanco neutronfgeno (comienzo del impulso). La segunda placa recibe seguidamente un impulso del mismo tipo que restablece el campo y hace desaparecer el haz del blanco (final del impulso). El frente de subida de los impulsos es del orden de 10 ns y el tiempo de desaparicion en el blanco es inferior a este valor. La duracion del impulso puede ajustarse a voluntad dentro de limites razonables retardando adecuadamente el segundo impulso con relacion al primero. En ciertos casos el tiempo de transito de los iones en las placas no es despreciable con respecto al tiempo durante el cual se aplica el incremento de tension. En estas circunstancias, se sustituye una de las placas por una lfnea de onda progresiva a la que se aplican sucesivamente los dos impulsos. El impulso de tension acompana asi al paquete de deuterones que produce el impulso. Los frentes de impulsos pueden reducirse, de este modo, a menos de 4 ns. Los generadores de tension escalonada estan transistorizados en sus primeras etapas. Los tubos de salida estan constituidos por valvulas de disco sellado que permiten obtener un incremento de tension de 1500 V en algunos nanosegundos. Los autores han utilizado un doble tetrodo de 50 MHz para los impulsos destinados a la lfnea de retardo. El sistema de deteccion emplea un dispositivo de centelleo y un fotomulti piicador cuyo circuito comprende un conjunto coincidencias-anticoincidencias, un analizador de tiempos y un registrador numerico. (author) [Russian] Nami razrabotana sistema, kotoraja daet vozmozhnost' poluchat' nejtronnye impul'sy nezavisimo ot reguliruemoj shiriny i chastoty sledovanija. Vremja narastanija i zatuhanija jetih impul'sov so- stavljaetporjadkaneskol'kihnanosekund. Dannaja sistema ispol'zuetsja pri provedenii impul'snyh i moduliruemyh opytov vysokoj chastoty. Dlja poluchenija nejtronnyh impul'sov s bystrym zatuhaniem primenjaetsja otklonenie puchka chistyh dejtonov, kotorye predvaritel'no byli uskoreny i otobrany. Iony, kotorye ne javljajutsja Dejtonami, byli ustraneny posle uskorenija v sortirovochnom magnite pri 10 Degree-Sign . Nami izuchalas' takzhe sistema otbora pered uskoreniem, kotoraja imela by preimushhestvo v vide umen'shennyh gabaritnyh razmerov. Puchok dejtonov prohodit cherez prostranstvo, nahodjashheesja mezhdu dvumja plastinkami, gde obychno imeetsja jelektrostaticheskoe pole, otklonjajushhee puchok na stenki diafragmy. Na pervuju plastinku napravljaetsja ochen' shirokij impul's naprjazhenija, kotoryj snimaet pole, i jeto delaetsja dlja togo, chtoby bystro napravit' puchok na mishen', generirujushhuju nejtrony (nachalo impul'sa). Zatem vtoraja plastinka poluchaet impul's togo zhe tipa, kotoryj vosstanavlivaet pole i snimaet puchok s misheni (konej impul'sa). Front narastanija impul'sov porjadka 10 nanosekund; vremja ischeznovenija s misheni nizhe jetogo poslednego znachenija. Prodolzhitel'nost' impul'sa mozhet svobodno regulirovat'sja v razumnyh predelah sootvetstvujushhej zaderzhkoj vtorogo impul'sa po otnosheniju k pervomu. V opredelennyh sluchajah vremja proleta ionov v plastinkah imeet opredelennoe znachenie po otnosheniju k postepennoj prodolzhitel'nosti, kotoraja k jetomu vremeni primenjaetsja. Dalee odnu iz plastinok zamenjajut uvelichivajushhejsja liniej, k kotoroj posledovatel'no primenjajutsja dva impul'sa. 'Impul's naprjazhenija soprovozhdaet, takim obrazom, sgustok dejtonov, kotoryj daet impul's. Stupenchatye generatory naprjazhenija v pervyh stupenjah imejut tranzistory. Vyhodnymi lampami javljajutsja jelektronnye lampy s diskovymi vyvodami, kotorye dajut vozmozhnost' poluchat' seriju 1500 vol't v techenie neskol'kih nanosekund. My ispol'zuem dvojnye tetrody po 50 mgc dlja impul'sov, prednaznachennyh dlja linii zaderzhki. V sisteme obnaruzhenija primenjaetsja scintilljacionno-fotoumnozhajushhee ustrojstvo, cep' kotorogo sostoit iz shemy sovpadenij-antisovpadenij, vremennogo analizatora i cifrovogo samopisia informacii. (author)

  15. The polarized neutron spectrometer REMUR at the pulsed reactor IBR-2

    International Nuclear Information System (INIS)

    Aksenov, V.L.; Zhernenkov, K.N.; Kozhevnikov, S.V.; Nikitenko, Yu.V.; Petrenko, A.V.; Lauter, H.J.; Lauter-Pasyuk, V.

    2004-01-01

    At the Laboratory of Neutron Physics (JINR, Dubna) the new polarized neutron spectrometer REMUR has been constructed and commissioned. The spectrometer REMUR is dedicated to investigations of multilayers and surfaces by polarized neutron reflection and of the inhomogeneous state of solids by diffuse small-angle polarized neutron scattering. The spectrometer operates in the neutron wavelength interval 1-10 Angstroem. In the reflectometry mode it allows one to complete polarization analysis and neutron position-sensitive detection within the solid angle of scattering 2.2·10 -4 rad. The spectrometer ensures good statistics of the reflectometric data in the scattering wave vector interval 3·10 -3 - 5·10 -1 Angstroem -1 . In the small-angle scattering mode the spectrometer allows the investigation of neutron scattering processes without spin-flip over the detector's neutron registration solid angle interval from 4·10 -3 to 10 -1 rad and the scattering wave vector interval from 0.006-0.15 to 0.03-0.7 Angstroem -1 , respectively

  16. Use of neutron activation analysis at the IBR-2 reactor for atmospheric monitoring

    International Nuclear Information System (INIS)

    Peresedov, V.F.; Ostrovnaya, T.M.; Strelkova, L.P.; Chinaeva, V.P.; Gundorina, S.F.

    1999-01-01

    The object of this work was the study of the possibilities of neutron activation analysis (NAA) for determination of elemental content of atmospheric aerosol. On examples of three Siberian regions it was shown that methodics of analysis allow to estimate the average level of suburban background (ALSB), scale of its regional, season and annual changes. Analysis of enrichment factors allows one to convince in presence of increased content of a row of heavy metals in atmospheric air of background regions what is the consequence of a global growing of technogenic impact

  17. Development of the SONIX software for the YuMO instrument at the IBR-2 reactor

    International Nuclear Information System (INIS)

    Kirilov, A.S.; Litvinenko, E.I.; Astakhova, N.V.; Murashevich, S.M.; Petukhova, T.B.; Yudin, V.E.; Gordelij, V.I.; Islamov, A.Kh.; Kuklin, A.I.

    2003-01-01

    The main results of the modernization of the software complex of the YuMO spectrometer are described. The comparison of the previous MS-DOS based software and new OS-9 based one is carried out. The advantages and disadvantages of each program are described. The main features of the new software complex and the results of its long-term operation are presented. It is shown that the software upgrade essentially improved the spectrometer control. (author)

  18. Fan analyzer of neutron beam polarization on REMUR spectrometer at IBR-2 pulsed reactor

    International Nuclear Information System (INIS)

    Nikitenko, Yu.V.; Ul'yanov, V.A.; Pusenkov, V.M.; Kozhevnikov, S.V.; Jernenkov, K.N.; Pleshanov, N.K.; Peskov, B.G.; Petrenko, A.V.; Proglyado, V.V.; Syromyatnikov, V.G.; Schebetov, A.F.

    2006-01-01

    The new spectrometer of polarized neutrons REMUR has been created and put in operation in the Frank Laboratory of Neutron Physics (JINR, Dubna). The spectrometer is dedicated to investigations of multiplayer structures and surfaces by registering the reflection of polarized neutrons and of the inhomogeneous state of solid matter by measuring the small-angle scattering of polarized neutrons. The spectrometer's working range of neutron wavelengths is 1.5-10 A. The spectrometer is equipped with a linear position-sensitive detector and a focused supermirror polarization analyzer (fan-like polarization analyzer) with a solid angle of neutron detection of 2.2x10 -4 rad. This article describes the design and the principle of operation of the fan analyzer of neutron polarization together with the results of its tests on a polarized neutron beam

  19. Arrangement of remote control of spectrometers on IBR-2M reactor

    International Nuclear Information System (INIS)

    Kirilov, A.S.; Murashkevich, S.M.; Okulov, R.Yu.; Petukhova, T.B.; )

    2009-01-01

    The principles of arranging and design features of the WebSonix system consisting of the central web-site and interface equipment with spectrometers are considered. The system allows one to reflect the actual statuses of all spectrometer components, view the measurements protocols, display the accumulative spectra, and control the course of the experiment on the spectrometers under control of the Sonix+ software package (Windows XP operational system). The system does not depend on the spectrometer characteristics and permits simple changes of their structure and easy adaptation to special features of spectrometric data representation. The system is based on PHP and Python scripts. The GNU/Linux Debian operational system and Apache 2 web server are installed on the web-site computer [ru

  20. Angular distributions of fast neutrons scattered by Al, Si, P, S and Zn; Distributions angulaires des neutrons rapides diffuses par Al, Si, P, S et Zn; Usloviya raspredeleniya bystrykh nejtronov, rasseyannykh alyuminiem, kremniem, fosforom i tsinkom; Distribuciones angulares de neutrones rapidos dispersados por Al, Si, P, S y Zn

    Energy Technology Data Exchange (ETDEWEB)

    Tstjkaija, K; Tanaka, S; Maeuyama, M; Tomita, Y [Japan Atomic Energy Research Institute, Tokai-Mtjea (Japan)

    1962-03-15

    Differential scattering cross-sections of Al, Si, P, S and Zn for fast neutrons have been measured in an energy range of 3.4 to 4.6 MeV by using the time-of-flight method. Angular distributions of the inelastically scattered neutrons are nearly isotropic in all cases. These results are discussed on the basis of the Hauser-Feshbach theory. (author) [French] Les sections efficaces differentielles de diffusion de Al, Si, P, S et Zn pour des neutrons rapides ont ete mesurees dans la gamme d'energies de 3,4 a 4,6 MeV, en employant la methode du temps de vol. Les distributions angulaires des neutrons diffuses inelastiquement sont presque isotropes dans tous les cas. Les auteurs analysent ces resultats en se fondant sur la theorie de Hauser-Feshbach. (author) [Spanish] Los autores han medido por el metodo del tiempo de vuelo las secciones eficaces diferenciales de dispersion del Al, Si, P, S y Zn para neutrones rapidos de energia comprendida entre 3,4 y 4,6 MeV. Las distribuciones angulares de los neutrones dispersados inelasticamente son casi isotropicas en todos los casos. Los autores analizan los resultados obtenidos basandose en la teoria de Hauser-Feshbach . (author) [Russian] Differentsial'no e sechenie rasseyaniya alyuminiya, kremniya, fosfora, sery i tsinka dlya bystrykh nejtronov izmereno v diapazone ehnergii ot 3,4 do 4,6 Megaehlektronvol't ispol'zovanie m metoda vremeni proleta. Uglovye raspredeleniya neuprugo rasseyannykh nejtronov yavlyayutsya pochti vo vsekh sluchayakh izotropnymi. Jeti rezul'taty obsuzhdayutsya na osnove teorii Hauzera-Feshbakha. (author)

  1. A fan analyzer of neutron beam polarization on the spectrometer REMUR at the pulsed reactor IBR-2

    International Nuclear Information System (INIS)

    Ul'yanov, V.A.; Pusenkov, V.M.; Pleshanov, N.K.

    2004-01-01

    The new spectrometer of polarized neutrons REMUR has been created and put in operation at the Frank Laboratory of Neutron Physics (JINR, Dubna). The spectrometer is dedicated to investigations of multilayer structures and surfaces by registering the reflection of polarized neutrons and of the inhomogeneous state of solid matter by measuring the small-angle scattering of polarized neutrons. The spectrometer's working range of neutron wavelengths is 1.5-10 Angstroem. The spectrometer is equipped with a linear position-sensitive detector and a focused supermirror polarization analyzer (the fan-like polarization analyzer) with a solid angle of polarized neutron detection of 2.2·10 -4 rad. This paper describes the design and the principle of operation of the fan analyzer of neutron polarization together with the results of the fan tests on a polarized neutron beam

  2. On the use of a composite moderator at the IBR-2 reactor: Advantages for the neutron-diffraction texture analysis of rocks

    Czech Academy of Sciences Publication Activity Database

    Bulavin, M. V.; Vasin, R.N.; Kulikov, S.A.; Lokajíček, Tomáš; Levin, D.M.

    2016-01-01

    Roč. 10, č. 4 (2016), s. 677-686 ISSN 1027-4510 Institutional support: RVO:67985831 Keywords : cold moderator * neutron-diffraction texture analysis * phase analysis * Rietveld method Subject RIV: DB - Geology ; Mineralogy

  3. Automation of registration of sample weights for high-volume neutron activation analysis at the IBR-2 reactor of FLNP, JINR

    International Nuclear Information System (INIS)

    Dmitriev, A.Yu.; Dmitriev, F.A.

    2015-01-01

    The 'Weight' software tool was created at FLNP JINR to automate the reading of analytical balance readouts and saving these values in the NAA database. The analytical balance connected to the personal computer is used to measure weight values. The 'Weight' software tool controls the reading of weight values and the exchange of information with the NAA database. The weighing process of a large amount of samples is reliably provided during high-volume neutron activation analysis. [ru

  4. Investigation of in-plane biaxial low cycle fatigued austenitic stainless steel AISI 321. II. Neutron diffraction stress analysis at the IBR-2 pulsed nuclear reactor

    International Nuclear Information System (INIS)

    Taran, Yu.V.; Balagurov, A.M.; Sheverev, S.G.; ); Schreiber, J.; Bomas, H.; Korsunsky, A.M.

    2007-01-01

    The in-plane biaxial low cycle fatigued sample of the cruciform geometry from austenitic stainless steel AISI 321 was investigated on the time-of-flight neutron Fourier stress-diffractometer. The lattice parameters in the austenite matrix and the martensite inclusions created during the fatigue cycling as well as the martensite volume fraction were measured along two mutually perpendicular planar axes of the sample of the cruciform geometry by using the strain neutron scanner. The phase total residual strain components were calculated using the stress equilibrium relations. The separation of the residual stresses into macro- and microstresses was performed using the mixture rule. The measurements of the applied load-phase elastic strain responses were carried out on a uniaxial load machine. The strong difference between the phase elastic moduli was found out

  5. 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)

  6. Use of Synthetic Polymers in Nuclear Emulsions for Fast-Neutron Dosimetry; Primenenie sinteticheskikh polimerov v yadernykh ehmul'siyakh dlya dozimetrii bystrykh nejtronov

    Energy Technology Data Exchange (ETDEWEB)

    Bradna, F. [Laboratorija Radiologicheskoj Dozimetrii Instituta Jadernykh Issledovanij CHSAN Praga, CSSR (Czech Republic)

    1967-01-15

    The paper describes the results of tests on the properties of hydrogen-enriched nuclear-track emulsions for detecting fast neutrons, which were prepared in the Radiological Dosimetry Laboratory of the Czechoslovak Academy of Sciences Nuclear Research Institute. It also compares the dosimetric characteristics of these new emulsions with those of the gelatin emulsions used up to the present. The most promising of the series of polymers synthesized in the laboratory were: (1) Polyvinylacetal of 2,4-disulphonic acid benzaldehyde (polymer No. 1); (2) The co-polymer of a-acetylaminoacrylic acid and N-vinylpyrrolidone (polymer No. 2). The author also studied the possibility of using polyvinyl alcohol solutions with a higher hydrogen content than the above polymers for saturating polymer-gelatin emulsions and for preparing from them films for use as proton radiators. Polymers No. 1 and No. 2 were tested beforehand in an ammonia emulsion. It was established that polymer No. 1 has no marked effect on the photochemical properties of the emulsions, whereas the physical and mechanical.properties of the polymer-gelatin emulsions are considerably better than those of normal gelatin emulsions. The polymers have good protective properties, and polymer No. 2; can be used even during physical ageing, since it retards this process only to a small extent. The photochemical properties of the polymer-gelatin emulsions remain practically unchanged during natural ageing, and their mechanical strength is still further increased. After these preliminary tests, polymers No.-1 and No. 2 were used as fillers for a nuclear-track emulsion, in quantities ranging from 50 to 70% of the total amount of protective colloid, the silver content of the emulsion remaining unchanged. To increase their efficiency further, the polymer-gelatin emulsions were saturated with hydrogen, which was passed through the liquid emulsion for a short period of time. When prepared, the emulsions were poured on a tri-acetate substrate 190-{mu}m thick, which was an effective proton radiator. The emulsions were irradiated with fast neutrons of fluence 1.56 x 10{sup 8} n/cm{sup 2} from an RaD-Be source. For increased efficiency of neutron detection, supplementary proton radiators such as polyvinyl alcohol (PVA), tri-acetate (T) and polyethylene (PE) of the optimum thickness were used during irradiation of the emulsion. Dosimetric analysis of the results gave the following: (1) The efficiency of detection was increased, in comparison with normal gelatin emulsions, by: (a) up to 25% when using polymers No. 1 and No. 2, depending on the degree of filling, and (b) 100% when polymer No. 1 was used in a hydrogen-saturated emulsion taken as a standard polymer-gelatin emulsion (SPGE), (2) When the optimum supplementary proton radiators (PVA, T, PE) were added to this SPGE, its detection efficiency was further increased to 330%. (author) [Russian] V dannoj rabote predlagajutsja rezul'taty ispytanij svojstv v Laboratorii radiologicheskoj dozimetrii IJaI ChSAN vodorodom obogashhennyh jadernyh jemul'sij, prednaznachennyh dlja registracii bystryh nejtronov i privoditsja sravnenie dozimetricheskih harakteristik jetih jemul'sij novogo tipa s harakteristikami do sih por ispol'zuemyh zhelatinovyh jemul'sij. Iz serii v laboratorii sintezirovannyh polimerov naibolee interesnymi okazalis': 1) olivinil'acetal' 2,4-disul'fokisloty benzaldegida (polimer N2 1); 2) sopolimer a-acetilaminoakrilovoj kisloty i N-vinilpirrolidona (polimer No 2). Otdel'no izuchalas' vozmozhnost' primenenija rastvorov polivinilovogo spirta s bolee vysokim soderzhaniem vodoroda po sravneniju s vysheukazannymi ispytannymi polimerami (No 1, No 2) dlja propityvanija polimero-zhelatinovyh jemul'sij i dlja prigotovlenija iz nego plenok v kachestve radiatora protonov. Polimery N21 i N9 2 primenjalis' predvaritel'no v ispytatel'noj ammiachnoj jemul'sii. Bylo ustanovleno, chto polimer No 1 ne okazyvaet zametnogo vlijanija na fotohimicheskie svojstva jemul'sij, odnako fiziko-mehanicheskie svojstva polimero-zhelatinovyh jemul'sij znachitel'no luchshe svojstv obychnyh zhelatinovyh jemul'sij. Polimery obladajut horoshimi zashhitnymi svojstvami i polimer No 2 prigoden dazhe v fizicheskom sozrevanii, poskol'ku on malo tormozit jetot process. V techenie estestvennogo starenija fotohimicheskie svojstva polimero-zhelatinovyh jemul'sij prakticheski ne izmenjalis' i eshhe dal'she znachitel'no povyshalas' ih mehanicheskaja prochnost'. V rezul'tate ukazannyh predvaritel'nyh opytov polimery No 1 i No 2 primenjalis' v kachestve napolnitelej jadernoj jemul'sii v kolichestve ot 50 do 70% po otnosheniju k obshhemu kolichestvu zashhitnogo kolloida, ne izmenjaja v dannoj jemul'sii soderzhanie serebra. Dlja dal'nejshego povyshenija jeffektivnosti jemul'sij polimero-zhelatinov'te jemul'sii nasyshhalis' vodorodom putem vremennogo propuskanija cherez ego zhidkuju jemul'siju. Gotovye jemul'sii nalivalis' na triacetatnuju podlozhku tolshhinoj 190 mikron, kotoraja javljaetsja v zhelaemom sluchae jeffektivnym radiatorom protonov. Jemul'sii obluchalis' bystrymi nejtronami plotnost'ju 1,56 * 108 nejtronov/sm{sup 2} ot istochnika (Ra - D - Be). S cel'ju uvelichenija jeffektivnosti registracii nejtronov, pri obluchenii jemul'sij ispol'zovalis' dobavochnye radiatory protonov tipa: polivinilovyj spirt (PVS), triacetat (T), polijetilen (PJe) optimal'noj tolshhiny. Obrabotka rezul'tatov s dozimetricheskoj tochki zrenija pokazala sledujushhie rezul'taty: 1. Po sravneniju s obychnymi zhelatinovymi jemul'sijami jeffektivnost' registracii povysilas': - do 25% v sluchae primenenija polimerov No 1 i No 2 v zavisimosti ot stepeni napolnenija; . - na 100% v sluchae primenenija polimera No 1 v vodorodom nasyshhennoj jemul'sii, prinjatoj v kachestve standarta polimero-zhelatinovoj jemul'sii (SPZhJe). 2. V sluchae primenenija optimal'nyh dobavochnyh radiatorov protonov (PVS, T, PJe) k ukazannoj jemul'sii SPZhJe, ee jeffektivnost' registrkcii povysilas' dal'she do 330%. (author)

  7. Analyser for fast single events; Analyseur d'evenements rapides simples; Analizator bystrykh odnokratnykh yavlenij; Analizador de sucesos rapidos no recurrentes

    Energy Technology Data Exchange (ETDEWEB)

    Sedlmeyer, J W; Patten, R B; Fussell, L Jr [Edgerton, Germeshausen And Grier, Inc., Las Vegas, NV (United States)

    1962-04-15

    An electronic analyser has been designed and constructed for use with single non-recurring transient signals. The signal, during passage along a coaxial line, is sampled instantaneously at a number of tap-off points, by means of a single short-duration gate pulse. Multipoint time-dissection is accomplished using a gate-duration and a time-interval between samples, which are independently adjustable from about 4 ns. The time-intervals may be programmed in non-linear array, and jitter is less than 0.5 ns. The speed of response is at present limited by diode characteristics. Each sampled voltage is stretched in a circuit which retains the voltage amplitude. A time-stretch by a factor of 10{sup 8} has been realized, with good stability. These data points may be commutated and transmitted over open-wire to low-frequency recording systems ; they may be converted to digital form for rapid data-processing, using conventional equipment; and/or they may be presented visually. The analyser is advantageous, compared with high-speed oscilloscopy, when large numbers of single-transients require individual analysis; such requirements exist for investigations into fluctuations in the response of systems, or for production-testing of components. The analyser is advantageous when the data-analysis must be accomplished quickly after the signal event occurs; it is not necessary to develop films or to read them. The analyser is also advantageous when the analysis-computation centre is located remotely from the event. Applications of this technique in the nuclear field are many. Fluctuation studies of reactors and subcritical assemblies may be carried out rapidly by pulsed neutron techniques. The build-up and decay characteristics of detectors may be determined, together with analysis of statistics and fluctuations. The pulse shape of the radiation wave from nuclear accelerators may be measured. Neutron-spectrometry using the time-of-flight method may be facilitated. Isomeric studies involving half-lives in the range 10-1000 ns, together with scattering investigations, may be carried out quickly and precisely. This work was supported by the United States Atomic Energy Commission. (author) [French] Les auteurs ont concu et realise un analyseur electronique destine a l'etude de signaux transitoires simples non recurrents. Lors de son passage le long d'une ligne coaxiale, le signal fait l'objet de prelevements instantanes a un certain nombre de points de branchement, au moyen d'une impulsion unique de declenchement tres breve venant d'un circuit porte. On procede a une dissection suivant le temps en des points multiples, en employant une duree de declenchement et un intervalle entre les prelevements; cette duree et cet intervalle peuvent etre ajustes independamment a partir de 4 ns environ. Les intervalles peuvent etre programmes d'une facon non lineaire, et l'instabilite de la case de temps est inferieure a 0,5 ns. La vitesse de reponse est actuellement limitee par les caracteristiques de la diode. Chaque tension prelevee est allongee dans un circuit qui en conserve l'amplitude. On a pu multiplier la largeur de l'impulsion par 10{sup 8}, tout en maintenant une stabilite satisfaisante. Ces donnees de repere peuvent faire l'objet d'une permutation et d'une transmission par fil nu a des enregistreurs a basse frequence; on peut les convertir sous forme numerique aux fins de depouillement rapide, en utilisant des appareils classiques; on peut aussi, le cas echeant, leur donner une presentation visuelle. L'analyseur est plus avantageux que les oscillographes a grande vitesse, ou il est necessaire d'analyser individuellement un grand nombre de signaux transitoires isoles; on est d'ailleurs oblige de proceder de meme pour etudier les fluctuations de reponse des systemes, ou pour faire des essais de production sur les elements constitutifs. L'analyseur presente aussi des avantages lorsqu'il faut analyser les donnees aussitot apres que le signal s'est manifeste; il n'est pas non plus necessaire de developper ni d'interpreter des pellicules. L'analyseur est egalement utile lorsque le centre de calcul et d'analyse est eloigne du lieu ou se produit l'evenement. Cette technique l5eut avoir de nombreuses applications dans le domaine nucleaire. Les techniques de faisceaux puises de neutrons permettent de proceder rapidement a des etudes sur les fluctuations des caracteristiques des reacteurs et des ensembles sous-critiques. En meme temps qu'on analyse les donnees statistiques et les fluctuations, on peut determiner les caracteristiques d'accumulation et de temps de decroissance des detecteurs. Il est egalement possible de mesurer la forme d'impulsion de l'onde de rayonnement emise par les accelerateurs nucleaires. D'autre part, la spectrometrie des neutrons par la methode du temps de vol peut etre facilitee. Enfin, cette technique permet d'effectuer avec rapidite et precision des etudes sur les isomeres dont les periodes sont comprises entre 10 et 1000 ns, de meme que des recherches sur la diffusion. (author) [Spanish] Los autores han proyectado y construido un analizador electronico destinado a utilizarse con senales transitorias no recurrentes. La senal, al pasar a lo largo de una linea coaxial, es probada instantaneamente en una serie de puntos, por medio de un impulso de puerta de corta duracion. La diseccion multipuntual en el tiempo se ejecuta recurriendo a una duracion de puerta y un intervalo de tiempo entre las muestras tomadas, que pueden ajustarse independientemente a partir de unos 4 ns. Los intervalos de tiempo pueden programarse en una disposicion no lineal y la inestabilidad es inferior a 0,5 ns. La rapidez de respuesta queda limitada actualmente por las caracteristicas de los diodos. Cada tension tomada es alargada en un circuito que conserva la amplitud de la tension. Se ha alcanzado una extension en el tiempo de 10{sup 8} veces, con buena estabilidad. Estos datos pueden conmutarse y transmitirse a sistemas de registro de baja frecuencia; se puede darles forma digital para facilitar un rapido tratamiento de los datos con el empleo de los dispositivos corrientes; y pueden tambien presentarse visualmente. Comparado con los oscilografos rapidos, el analizador es mas ventajoso cuando se trata de analizar individualmente grandes cantidades de fenomenos transitorios distintos y no recurrentes; tal es el caso del estudio de las fluctuaciones en la respuesta de sistemas o el ensayo de componentes producidos en serie. Tambien es preferible el analizador cuando el analisis de los datos debe efectuarse en seguida de ocurrir el fenomeno ''senal'', puesto que no es preciso revelar peliculas ni interpretarlas. Asimismo presenta ventajas cuando el centro de computo del analisis esta situado lejos del lugar del suceso. Tiene multiples aplicaciones en el campo de la energia nuclear. Facilita el rapido estudio de las fluctuaciones en los reactores y conjuntos subcriticos mediante la tecnica de las fuentes pulsantes de neutrones. Permite determinar las caracteristicas de formacion y descenso del impulso en los detectores y hacer analisis de estadisticas y fluctuaciones. Es posible registrar con el la forma del impulso de la onda de radiacion de los aceleradores nucleares. Facilita la espectrometria neutronica por el metodo del tiempo de vuelo. Permite efectuar con rapidez y exactitud estudios isomericos en que intervienen periodos de semidesintegracion entre limites de 10 y 1000 ns, juntamente con investigaciones sobre dispersion. La Comision de Energia Atomica de los Estados Unidos presto su apoyo a este estudio. (author) [Russian] Byl skonstruirovan i postroen ehlektronnyj analizator dlya ispol'zovaniya s odnokratnykh nepovtoryayushchikhsya perekhodyashchikh signalakh. Vo vremya prokhoda signala vdol' koaksial'noj linii mgnovenno v tselom ryade tochek proiskhodit otbor, chto delaetsya pri pomoshchi odnokratnogo korotkogo vremennogo selektornogo impul'sa. Razbivka vremeni na mnogochislennye otrezki dostigaetsya pri pomoshchi vremennogo selektornogo impul'sa i intervala vremeni mezhdu otborom obraztsov, prichem i tot i drugoj mogut regulirovat'sya nezavisimo drug ot druga, nachinaya priblizitel'no s 4 nanosekund. Intervaly vremeni mogut zadavat'sya v nelinejnom poryadke, a razbros mezhdu nimi ne prevyshaet 0,5 nanosekund. Do nastoyashchego vremeni skorost' otvetnoj reaktsii ogranichivaetsya kharakteristikami dioda. Kazhdoe otobrannoe napryazhenie rasshiryaetsya v konture, kotoryj sokhranyaet amplitudu ehtogo napryazheniya. Udalos' osushchestvit' rasshirenie po vremeni v 10{sup 8} raz s sokhraneniem khoroshej ustojchivosti. Tochki pokazanij mogut soobshchat'sya i peredavat'sya po otkrytomu provodu v nizkochastotnoe registriruyushchee ustrojstvo, oni mogut byt' prevrashcheny v tsifrovye dannye dlya bystroj ikh obrabotki s pomoshch'yu obychnogo oborudovaniya; krome togo, ili vmesto ehtogo, oni mogut byt' dany vizual'no. Analizator imeet preimushchestva po sravneniyu s vysokoskorostnoj ostsiloskopiej, kogda trebuetsya provodit' individual'nyj analiz bol'shogo chisla odnokratnykh perekhodyashchikh signalov; ehto trebuetsya pri izuchenii kolebanij otvetnykh reaktsij sistem ili pri proizvodstvennykh ispytaniyakh komponentov. Analizator imeet preimushchestva, kogda analiz dannykh dolzhen proizvodit'sya neposredstvenno za poyavleniem signala; otpadaet neobkhodimost' proyavlyat' plenki ili prochityvat' ikh. Analizator udoben takzhe v tekh sluchayakh, kogda schetno-analiziruyushchij tsentr raspolozhen daleko ot mesta poyavleniya signala. EHtot metod shiroko primenyaetsya v oblasti yadernoj ehnergii. Metod pul'siruyushchikh nejtronov mozhet byt' primenen dlya bystrogo izucheniya kolebanij rezhima reaktorov i podkriticheskikh sborok. Mogut byt' opredeleny parametry nakopleniya i raspada detektorov i odnovremenno provodit'sya analiz statisticheskikh dannykh i kolebanij. Mozhet izmeryat'sya forma impul'sov radiatsionnykh voln, proizvodimykh yadernymi uskoritelyami. S pomoshch'yu metoda izmereniya vremeni proleta mozhno provodit' nejtronnuyu spektrometriyu. Mozhno provodit' bystrye i tochnye izomericheskie issledovaniya v otnoshenii izomerov s poluperiodom raspada v intervale ot 10 do 1000 nanosekund, a takzhe bystro i tochno opredelyat' rasseyanie. EHta rabota vypolnyalas' pri sodejstvii Komissii po atomnoj ehnergii SSHA. (author)

  8. RBE of Monoenergetic Fast Neutrons: Cytogenetic Effects in Maize; EBR des Neutrons Rapides Monoenergeniques: Effets Cytogenetiques sur le Mais; Obeh monoehnergeticheskikh bystrykh nejtronov: tsitogeneticheskie izmeneniya u kukuruzy; EBR de los Neutrones Rapidos Monoenergeticos: Efectos Citogeneticos en el Maiz

    Energy Technology Data Exchange (ETDEWEB)

    Smith, H. H.; Bateman, J. L.; Quastler, H.; Rossi, H. H. [Biology and Medical Departments, Brookhaven National Laboratory, Upton, NY (United States)

    1964-05-15

    The maize used in these experiments has the advantage for RBE studies of yielding a basically first-order dose-response curve with low as well as with high LET radiations. An exposure apparatus was used which produced essentially equal dose rates in five rings of seeds placed so as to intercept neutrons of 0.43, 0.65, 1.00, 1.50 and 1.80 MeV. The mutant sectors produced in leaves are believed to be due mostly to simple chromosome breakage and deletion. Experiments were performed at dosages that gave responses which were linear, below saturation levels, and overlapping in range for the monoenergetic fast neutrons and 250 kVp X-rays. RBE values, calculated from relative slopes of linear-regression lines for neutrons and X-rays ranged from 42 to 135 with an overall average of about 70. Fast neutrons of 0.43 MeV energy were the most efficient, of those used, in producing g{sub 2} mutant sectors. (author) [French] Pour les etudes sur l'EBR, le maft utilise au cours des experiences offre l'avantage de donner une courbe dose-reponse qui est essentiellement de premier ordre, que le TLE du rayonnement soit faible ou eleve. Les auteurs ont utilise un appareil d'irradiation assurant des debits de dose pratiquement egaux dans cinq couronnes de semences disposees de maniere a intercepter les neutrons de 0,43, 0,65, 1,00, 1,50 et 1,80 MeV. On pense que les secteurs mutants produits dans les feuilles sont dus essentiellement a une rupture et une disparition de chromosomes simples. Les auteurs ont fait des experiences a des doses qui ont donne des reponses lineaires, inferieures au niveau de saturation et se chevauchant dans le cas des neutrons rapides et des rayons X de 250 kV-crete. Les valeurs de l'EBR calculees d'apres la comparaison des pentes des courbes de regression lineaire pour les neutrons et les rayons X varient de 42 a 135, avec une valeur moyenne d'environ 70. Parmi les neutrons utilises, les neutrons rapides de 0,43 MeV ont ete les plus efficaces pour produire des secteurs mutants g{sub 2}. (author) [Spanish] La variedad de maiz utilizada en los experimentos descritos presenta la ventaja, desde el punto de vista del estudio de la EBR, de proporcionar una curva dosis-respuesta que es basicamente de primer grado, tanto para las radiaciones de TLE elevada como para las de TLE baja. Los autores emplearon un aparato de exposicion que produce intensidades de dosis esencialmente iguales en cinco anillos de semillas colocadas de modo que intercepten a los neutrones de 0,43, 0,65, 1,00 1,50 y 1,80 MeV. Se supone que los sectores mutantes producidos en las hojas se deben en su mayor parte a una simple ruptura y eliminacion de cromosomas. Se realizaron experimentos con dosis adecuadas para obtener respuestas lineales, inferiores al valor de saturacion, y tales que los intervalos correspondientes a los neutrones rapidos monoenergeticos y a los rayos X de 250 kVp se superpongan parcialmente. Los valores de la EBR calculados a base de las pendientes comparadas de las curvas de regresion de primer grado para los neutrones y los rayos X respectivamente, varian entre 42 y 135, con una media global del orden'de 70. De todos los neutrones rapidos utilizados en los experimentos, los mas eficaces para producir sectores mutantes g{sub 2} fueron los de 0,43 MeV. (author) [Russian] Kukuruza, ispol'zovannaja v jetih jeksperimentah, obladaet preimushhestvom dlja izuchenija OBJe pri poluchenii krivoj pervogo porjadka zavisimosti reakcii ot dozy dlja izuchenij s nizkim i vysokim LPJe. Primenjalas' ustanovka dlja obluchenija, kotoraja obespechivala po sushhestvu ravnye moshhnosti doz dlja raspolozhennyh v kol'cevom porjadke pjati rjadov semjan pri obluchenii nejtronami s jenergiej 0,43, 0,65, 1,00, 1,50 i 1,80 Mjev. Sektory mutantov, poluchaemye v list'jah, kak polagajut, dolzhny, glavnym obrazom, uproshhat' razryv i uterju hromosom. Byli provedeny jeksperimenty pri urovnjah doz, kotorye vyzyvali otvetnye reakcii s linejnoj zavisimost'ju nizhe urovnja nasyshhenija i perekryvalis' v predele dlja monojener- geticheskih bystryh nejtronov i dlja rentgenovskih luchej s naprjazheniem 250 kv. Velichiny OBJe, raschitannye v rezul'tate otnositel'nogo naklona linejnyh regressivnyh linij dlja nejtronov i rentgenovskih luchej, nahodilis' v predelah ot 42 do 135 so srednej velichinoj primerno 70. Bystrye nejtrony s jenergiej 0,43 Mjev byli naibolee jeffektivnymi sredi teh, kotorye ispol'zovalis' pri poluchenii mutantov sektorov g{sub 2}. (author)

  9. Reactivity coefficients by perturbation theory; Calcul des coefficients de re activite par la theorie des perturbations; Koehffitsienty reaktivnosti, opredelennye pri pomoshchi teorii vozmushchenij; Determinacion, de coeficientes de reactividad con ayuda de la teoria de las perturbaciones

    Energy Technology Data Exchange (ETDEWEB)

    Webster, J W [International Atomic Energy Agency, Vienna (Austria)

    1962-03-15

    (MCBR). Al calcular la reactividad, se comprueba que el coeficiente correspondiente a la densidad neta del mercurio en el primer proyecto del MCBR es negativo en algunas regiones, y positivo en otras. Es negativo en las regiones de peso estadistico maximo y en las que los cambios de densidad serian mayores al variar la potencia. Por lo tanto, el coeficiente global de densidad del mercurio es negativo, esto es, el coeficiente de vacios es positivo, lo que constituye una condicion que implica peligro. En la formulacion de dos grupos, se aprecia facilmente que modificaciones es preciso introducir en el diseno para que el coeficiente de cavidad sea negativo. Nuevas investigaciones demostraron que era posible introducir dichas modificaciones, lograndose establecer para el MCBR un diseno cuyo coeficiente de vacios es negativo. (author) [Russian] Razvitie formuly teorii vozmushchenij daet khoroshuyu vozmozhnost' ispol'zovat' odin iz glavnykh metodov matematicheskogo issledovaniya, t.e. proizvesti dejstvie po analogii ot prostogo k bolee slozhnomu. V ehtom doklade: a) Rassmatrivaets ya formulirovka teorii vozmushchenij v kachestve metoda rascheta koehffitsientov reaktivnosti. On sostoit, glavnym obrazom, iz razvitiya differentsial'nog o uravneniya dlya sopryazhennogo potoka kak postoyannoj funktsii polozheniya i letargii, vyvodimoe po analogii ot odnoj gruppy differentsial'nog o uravneniya dlya sopryazhennogo potoka. b) Daetsya primenenie dvukhgruppovoj formy teorii vozmushchenij dlya kipyashchego reaktorarazmnozhitelya na bystrykh nejtronakh s rtutnym teplonositelem (MCBR). Vidno, chto koehffitsient reaktivnosti rtuti nizshej plotnosti v khode pervogo ispytaniya proekta MCBR yavlyaetsya otritsatel'nym dlya nekotorykh oblastej i polozhitel'nym dlya drugikh. Odnako on yavlyaetsya otritsatel'nym dlya oblastej naivysshego statisticheskogo vesa i tam, gde izmenenie plotnosti s izmeneniem ehnergii okazyvaetsya naibol'shim. Obshchij koehffitsient plotnosti rtuti yavlyaetsya, takim

  10. Critical experiments and nuclear calculations - LAMPRE-I; Experiences critiques et calculs nucleaires concernant le LAMPRE-I; Kriticheskie opyty i yadernye raschety - LAMPRE-I; Experimentos criticos u calculos nucleares relativos al LAMPRE-I

    Energy Technology Data Exchange (ETDEWEB)

    Battat, M E [Los Alamos Scientific Laboratory, University of California, Los Alamos, NM (United States)

    1962-03-15

    utilise la methode S{sub n} pour resoudre le probleme du transport neutronique. La comparaison entre les valeurs calculees et les valeurs mesurees des parametres, tels que le coefficient thermique, l'efficacite des barres de controle et la masse critique, presente aussi de l'interet pour evaluer le degre de confiance que l'on peut accorder aux calculs des bureaux d'etudes. (author) [Spanish] Como parte de un programa de ensayos de combustibles de plutonio para reactores reproductores de neutrones rapidos, se ha construido y puesto en marcha en el Los Alamos Scientific Laboratory un reactor experimental de 1 MW refrigerado por sodio, cuyo cuerpo contiene una aleacion fundida de plutonio y hierro (90 atomos por ciento de Pu y 10 atomos por ciento de Fe; punto de fusion: 410 deg. C). La reactividad se regula por medio de un reflector de acero inoxidable y de cuatro barras de control de niquel situadas fuera del nucleo. Se han llevado a cabo experimentos a temperaturas (isotermicas) de 80, 160 y 480 deg. C en el cuerpo, a fin de determinar la masa critica y la eficacia del reflector a cada una de esas temperaturas. Tambien se midio la eficacia de las barras de control, por registro de los periodos y del coeficiente termico de la reactividad. Aplicando el metodo S{sub n} de resolucion del problema del transporte neutronico, se efectuaron calculos para determinar los parametros nucleares basicos del reactor. La comparacion entre los valores calculados y los valores medidos de parametros tales como el coeficiente termico, la eficacia de las barras de control y la masa critica, presenta tambien interes en lo que se refiere a la evaluacion del grado de confianza que puede atribuirse a los calculos del proyectista. (author) [Russian] V kachestve chasti programmy po razvitiyu plutonievogo topliva dlya reaktorov-razmnozhitele j na bystrykh nejtronakh Los-Alamosskaya nauchnaya laboratoriya skonstruirovala i ehkspluatiruet ispytatel'nyj reaktor s natrievym okhlazhdeniem moshchnost'yu v

  11. A punched-card library of neutron cross-sections and its use in the mechanized preparation of group cross-sections for use in Monte Carlo, Carlson S{sub n} and other multi-group neutronics calculations on high-speed computers

    Energy Technology Data Exchange (ETDEWEB)

    Parker, K [Atomic Weapons Research Establishment, Aldermaston (United Kingdom)

    1962-03-15

    vklyuchayut mnogogruppovoe transportnoe priblizhenie i polnuyu obrabotku anizotropnogo rasseyaniya, ispol'zuya momenty mnogochlena Lezhandra matritsy peredachi rasseyaniya. Printsipy obrazovaniya gruppovoj postoyannoj obsuzhdayutsya i illyustriruyutsya pri pomoshchi opisaniya sistem gruppovykh postoyannykh, podkhodyashchikh dlya raschetov reaktorov na bystrykh nejtronakh. Obsuzhdayutsya takie prakticheskie problemy, kak ehmpiricheskoe sogla- sovanie gruppovykh postoyannykh dlya vosproizvodstva integral'nykh rezul'tatov i prive-denie mnogogruppovoj sistemy postoyannykh k malogruppovoj sisteme. (author)

  12. amaranthus spp.

    African Journals Online (AJOL)

    DR. AMINU

    (French),. Amaranto, bredo. (Portuguese)};. Amaranthus tricolor L. {Amaranth, Joseph's coat. (English), Amarante .... only an excellent nutritional food for the AIDS sufferer, but those .... Aujeszky virus (ADV) in IB-RS-2 pig cell cultures and.

  13. The Biological Effect of Fast Neutrons and High-Energy Protons; Effets Biologiques des Neutrons Rapides et des Protons de Haute Energie; Biologicheskoe dejstvie bystrykh nejtronov i protonov vysokikh ehnergii; Efectos Biologicos de los Neutrones Rapidos y de los Protones de Elevada Energia

    Energy Technology Data Exchange (ETDEWEB)

    Moskalev, Ju. I.; Petrovich, I. K.; Strel' cova, V. N.

    1964-03-15

    The paper gives the results of comparative experiments on the effects of fast neutrons and high-energy protons (500 MeV) on life expectancy, peripheral blood, incidence and rate of appearance of tumours in the rat as a function of administered dose and time of observation. The neutron experiment was performed on 573 and the proton experiment on 490 white rats. The animals irradiated with fast neutrons were given doses between 8.5 and 510 rad, and those irradiated with protons received doses between 28 and 1008 rad. The effective doses for the acute, sub-acute and chronic forms of sickness were established for fast neutrons and for protons. LD{sub 50/30} for neutrons was 408 and for protons 600 rad, and the corresponding LD{sub 50}/{sub 120} values were 380 and 600 rad. The conditions governing rat mortality were analysed both in the early and the later stages of the experiment. It is shown that the average life expectancy of rats irradiated with fast neutrons does not depend on sex. The shape of the dose-effect curve for the various peripheral-blood indexes is strongly dependent not only on the radiosensitivity of the blood cells in question but also on the time of observation. It may change greatly in time for one and the same index. A considerable time after irradiation with either fast neutrons or protons, benign and malignant tumours appear in different tissues of the rats, including the haemopoeitic tissues, mammary glands, pituitary, uterus, ovaries, prostate gland, testicles, liver, kidneys, lungs, gastro-intestinal tract, subcutaneous tissue, lymph nodes, urinary bladder, etc. The over-all incidence of tumours and the number of cases of multi centred neoplasms in females are two to three times higher than in males. The minimum tumour dose for the mammary glands with neutron irradiation is apparently rather less than 42.5 rad. The maximum incidence of tumours of the pituitary is found after irradiation with a dose of 42.5 rad.- At this same dose leucosis and tumour of the thyroid gland also appear. With proton irradiation, the minimum tumour dose for haemopoietic tissue and the thyroid gland is in the neighbourhood of 250 rad, for the testicles 300 rad, for the prostate, the pancreas and the subcutaneous tissue 100 rad. After irradiation with fast neutrons the incidence of tumours of the testicles, the large intestine, the kidneys and the liver is increased at doses between 42.5 and 85 rad. The same is true for tumours of the skin and the subcutaneous tissue at a dose of 85 rad. With fast neutron irradiation tumours appeared at approximately three to five times lower radiation doses than with proton irradiation. (author) [French] Le memoire expose les resultats d'experiences visant a comparer l'e ffe t des neutrons rapides et celui des protons de haute energie (500 MeV) sur la duree de vie, le sang peripherique, la frequence et la rapidite d'apparition des tumeurs chez le rat, en tenant compte de la dose efficace et du delai d'observation. Les travaux ont porte sur 573 rats blancs pour les neutrons et sur 490 rats blancs pour les protons. Les animaux etaient exposes a des doses de neutrons rapides de 8,5 a 510 rad et a des doses de protons de 28 a 1008 rad. Pour les neutrons rapides et les protons, les auteurs ont determine les valeurs des doses effectives aiguees, sub-aiguees et chroniques. La DL{sup 30}{sub 50} est de 408 rad pour les neutrons et de 600 rad pour les protons; la DL{sup 120}{sub 50} s'eleve a 380 et 600 rad, respectivement. On a procede a une etude critique des lois qui regissent la mortalite des rats a breve echeance et apres des delais prolonges. D'apres les constatations, la survie moyenne des rats irradies par des neutrons rapides est independante de leur sexe. En ce qui concerne les differents indices du sang peripherique, la forme de la courbe dose/effet depend dans une forte mesure, non seulement de la radiosensibilite des cellules correspondantes du sang, mais aussi de la duree d'observation. Elle peut subir des variations sensibles en fonction du temps pour un seul et meme indice. Longtemps apres une irradiation par des neutrons rapides ou par des protons, on constate chez le rat l'apparition de tumeurs benignes et malignes dans divers tissus, notamment dans le tissu hematopoie tique, les glandes mammaires, l'hypophyse, l'uterus, les ovaires, la prostate, les testicules, la thyroide, la glande cervicale, le pancreas, les glandes surrenales, le foie, les reins, les poumons, le tractus gastro-intestinal, le tissu cellulaire sous-cutane, les ganglions lymphatiques, la vessie, etc. La frequence globale des tumeurs et le nombre des apparitions simultanees de neoplasmes en plusieurs endroits ont ete deux a trois fois plus eleves chez les femelles que chez les males. La dose minimum de neutrons necessaire pour provoquer une tumeur des glandes mammaires semble legerement inferieure a 42,5rad. La frequence des tumeurs de l'hypophyse est la plus elevee lorsque la dose est de 42,5 rad. A cette meme dose,. on constate l'apparition de leucoses et de tumeurs de la thyroide. Lors d'une irradiation par des protons, la dose minimum necessaire pour provoquer une tumeur est de l'ordre de 250 rad pour le tissu hematopoietique et la thyroide, de 300 rad pour les testicules et de 100 rad pour la prostate et le tissu cellulaire sous-cutane. Lors d'une irradiation par les neutrons rapides, les tumeurs des testicules, du gros intestin, des reins et du foie sont plus frequentes pour 42,5 a 85 rad et les tumeurs de la peau et du tissu cellulaire sous-cutane pour 85 rad. Dans le cas d'une irradiation par neutrons rapides, les tumeurs se produisent a des doses inferieures (d'environ 3 a 5 fois) aux doses de protons. (author) [Spanish] Los autores presentan los resultados de experimentos efectuados con miras a comparar el efecto de los neutrones rapidos y el de los protones de elevada energia (500 MeV) sobre la duracion de la vida, las caracteristicas de la sangre periferica, asi como la frecuencia y rapidez de formacion de tumores en la rata, en funcion de la dosis aplicada y del tiempo transcurrido a partir de' la irradiacion. En el experimento con neutrones utilizaron 573 ratas blancas y en el experimento con protones, 490. Expusieron los animales a dosis neutronicas de 8,5 a 510 rad, y dosis protonicas comprendidas entre 28 y 1008 rad. Tanto para los neutrones rapidos como para los protones, establecieron el valor de la dosis efectiva aguda, subaguda y cronica. La DL{sup 30}{sub 50} para los neutrones asciende a 408 rad y a 600 rad para los protones; las respectivas dosis DL{sup 120}{sub 50} son 380 rad y 600 rad. Los autores estudiaron las leyes que rigen la mortalidad de los sujetos en experimentos breves y prolongados. Demuestran que la sobrevivencia de los mismos, cuando se ios irradia con neutrones rapidos, es independiente del sexo. La forma de la curva dosis/efecto para los diversos Indices de la sangre periferica no solo depende de la radiosensibilidad de las celulas sanguineas correspondientes, sino tambien del perfodo de observacion. Puede sufrir modificaciones sensibles en funcion del tiempo para un mismo indice. Algun tiempo despues de la irradiacion, tanto con neutrones rapidos como con protones, se observan en las ratas tumores de caracter benigno o maligno en diversos tejidos, entre ellos en los de los arganos hematopoyeticos, las glandulas mamarias, la hipofisis, el utero, los ovarios, la prostata, los testiculos, la tiroides, el timo y el pancreas, las glandulas suprarrenales, el higado, los rinones, los pulmones, el tracto gastrointestinal, el tejido hipodermico, los ganglios linfaticos, la vejiga, etc. La frecuencia total de los tumores y el numero de casos de formacion multicentrica de neoplasias es de 2 a 3 veces mayor en las hembras que en los machos. La dosis tumorigena minima en las glandulas mamarias, en la irradiacion neutronica, parece ser algo inferior a 42,5 rad. La frecuencia maxima de los tumores de la hipofisis se observa despues de la irradiacion con una dosis de 42,5 rad. Con la misma dosis tambien se manifiestan leucosis y tumores de la tiroides. En la irradiacion protonica, la dosis tumorigena minima es del orden de 250 rad para lee tejidos hematopoyeticos y la tiroides, de 300 rad para los testiculos, y de unos 100 rad para la prostata, el pancreas y el tejido hipodermico. Despues de la irradiacion con neutrones rapidos, la frecuencia de la aparicion de tumores en los testiculos, el intestino grueso, los rinones y el higado, presenta un aumento para dosis entre 42,5 y 85 rad, y en la piel y el tejido hipodermico ocurre lo mismo para dosis de 85 rad. En el caso de la irradiacion con neutrones rapidos, los tumores aparecen con dosis de 3 a 5 veces inferiores a las dosis protonicas. (author) [Russian] Predstavljajutsja rezul'taty sravnitel'nyh jeksperimentov po izucheniju dejstvija bystryh nejtronov i protonov vysokih jenergij (500 Mjev) na prodolzhitel'nost' zhizni, perifericheskuju krov', cha sto tu i skorost' pojavlenija opuholej u krys v zavisimosti o t dozy vozdejstvija i sroka nabljudenija. Opyt s nejtronami postavlen na 573, s protonami na 490 belyh krysah. Bystrymi nejtronami zhivotnyh obluchali v dozah ot 8,5 do 510 rad, protonami ot 28 do 1008 rad. Dlja bystryh nejtronov i protonov ustanovleny velichiny ostro, podostro i hronicheski jeffektivnyh d o z . LD{sub 50/30} dlja nejtronov ravna 408, dlja protonov 600 rad, a LD{sub 50/120} so otvetstvenno 380 i 600 rad. Proanalizirovany zakonomernosti vymiranija krys v rannie i pozdnie sroki jeksperimenta. Pokazano, chto srednjaja prodolzhitel'nost' zhizni krys, obluchennyh bystrymi nejtronami, ne zavisit ot pola. Forma krivoj doza-jeffekt dlja otdel'nyh pokazatelej perifericheskoj krovi sushhestvenno zavisit ne tol'ko ot radiochuvstvitel'nosti sootvetstvujushhih kletok krovi, no i ot sroka nabljudenija. Ona mozhet sushhestvenno izmenjat'sja vo vremeni dlja odnogo i t o go zhe pokazatelja. V otdalennye sroki posle obluchenija kak bystrymi nejtronami, tak i protonami u krys voznikajut dobrokachestvennye i zlokachestvennye opuholi razlichnyh tkanej, v tom chisle krovotvornoj, molochnyh zhelez, gipofiza, matki, jaichnikov predstatel'noj zhelezy, semennikov, shhitovidnoj zhelezy, zobnoj i podzheludochnoj zhelez, nadpochechnikov, pecheni, pochek, l e g kih, zheludochno-kishechnogo trakta, podkozhnoj kletchatki, limfaticheskih u z lov, mochevogo puzyrja i drugih. Summarnaja chastota opuholej i chislo sluchaev mul'ticentricheskogo vozniknovenija novoobrazovanij u samok v 2 - 3 raza vyshe, chem u samcov. Minimal'naja opuholevaja doza dlja molochnyh zhelez pri obluchenii nejtronami, po-vidimomu, neskol'ko nizhe 42,5 rad. Maksimal'naja chastota opuholej gipofiza obnaruzhivaetsja posle obluchenija v doze 42,5 rad. Pri jetoj zhe doze voznikajut lejkozy i opuholi shhitovidnoj zhelezy. Pri obluchenii protonami minimal'naja opuholevaja doza dlja krovotvornoj tkani i shhitovidnoj zhelezy nahoditsja v predelah 250 rad, dlja semennikov - 300 rad, dlja predstatel'noj, podzheludochnoj zhelez , podkozhnoj kletchatki - 100 rad. Posle obluchenija bystrymi nejtronami chastota opuholej semennikov, tolsto go kishechnika, pochek, pecheni okazyvaetsja uvelichennoj pri dozah 42,5 - 85 rad, kozhi i podkozhnoj kletchatki pri doze - 85 rad. Po sravneniju s protonami pri obluchenii bystrymi nejtronami opuholi voznikajut ot men'shih (primerno v 3 - 5 raz) doz obluchenija. (author)

  14. The Pulsed Neutron Technique Applied to Fast Non-Multiplying Assemblies; Application de la Methode des Neutrons Pulses aux Assemblages Non Multiplicateurs a Neutrons Rapides; Primenenie metoda impul'snykh nejtronov pri izuchenii povedeniya bystrykh nejtronov v nerazmnozhayushchikh sborkakh; Aplicacion de la Tecnica de los Neutrones Pulsados a Conjuntos Rapidos de Materiales No Multiplicadores

    Energy Technology Data Exchange (ETDEWEB)

    Beghian, L. E.; Wilensky, S. [Massachusetts Institute of Technology, Cambridge, MA (United States)

    1965-10-15

    A nanosecond pulsed Van de Graaff accelerator has been used to study the behaviour of fast neutrons in non-multiplying metal assemblies. A pulsed neutron source technique has been utilized to measure fast non-elastic cross-sections for iron. The method employed is similar to that used to measure absorption cross-sections in thermal assemblies, with the exception that the fast decay times are of the order of nanoseconds rather than microseconds. Nanosecond bursts of monoenergetic neutrons are injected into various size iron assemblies. The neutron flux in these assemblies is observed to decay exponentially with a characteristic decay constant. The decay constant is composed of a sum of terms which represent neutron loss due to leakage and energy degradation. Energy degradation represents a neutron loss since a biased neutron detector is used. The removal term due to elastic and nonelastic scattering can be determined by measuring the decay constant as a function of assembly size. A theoretical development is presented for calculating the fraction that the elastic scattering contributes to the removal term, hence the non-elastic cross-section can be determined. The theoretical treatment for calculating the elastic contribution has been verified experimentally. The non-elastic cross-section for iron has been measured by this technique for primary neutron energies between 0.8 and 1.5 MeV. The pulsed source technique described above has been used to measure decay constants for lead slabs. The experiment approximates the assumptions which are generally made when solving the time-dependent Boltzmann transport equation (i.e. one-dimension, one-velocity). Decay constants have been measured for 28 in x 32 in lead slabs of 2, 4, 6 and 8-in thickness. The results, after being corrected for energy degradation and finite assembly, are compared with the approximate solutions of the Boltzmann transport equation. (author) [French] Les auteurs ont utilise un accelerateur Van de Graaff a impulsions de l'ordre de la nanoseconde pour etudier le comportement de neutrons rapides dans des assemblages metalliques non multiplicateurs. Ils ont mesure les sections efficaces non elastiques du fer pour les neutrons rapides. La methode employee est semblable a celle qu'on utilise pour mesurer les sections efficaces d'absorption dans des assemblages a neutrons thermiques, avec cette difference que les temps de decroissance pour les neutrons rapides sont de l'ordre de la nanoseconde et non de la microseconde. Des bouffees de neutrons monoenergetiques d'une nanoseconde sont introduites dans des assemblages en fer de dimensions diverses. On remarque que dans ces assemblages le flux de neutrons decroit exponentiellement avec une constante de decroissance caracteristique. La constante de decroissance est composee d'une somme de termes qui representent la perte de neutrons due aux fuites et a la degradation en energie. La degradation en energie represente une perte de neutrons, car un detecteur de neutrons dont les donnees sont entachees d'une erreur systematique est utilise. On peut determiner le terme correspondant a la diffusion elastique et inelastique en mesurant la constante de decroissance consideree comme une fonction des dimensions de l'assemblage. Suit un developpement theorique pour le calcul de la fraction de ce terme qui est due a la diffusion elastique et, par consequent, pour la determination de la section efficace non elastique. Le procede theorique de calcul de cette fraction a fait l'objet de verifications experimentales. Les auteurs ont mesure la section efficace non elastique du fer par cette methode pour des energies de neutrons primaires comprises entre 0,8 et 1,5 MeV. La methode de la source puisee decrite ci-dessus a ete utilisee pour mesurer des constantes de decroissance pour des plaques de plomb. Les conditions de l'experience sont approximativement conformes aux hypotheses generalement admises lorsqu'on resout l'equation de transport de Boltzmann qui est fonction du temps (c'est-a-dire une dimension, une vitesse). Les constantes de decroissance ont ete mesurees pour des plaques de plomb de 70 cm x 80 cm et de 5, 10, 15 et 20 cm d'epaisseur. Apres correction pour tenir compte de la degradation en energie et des dimensions finies de l'assemblage, les resultats sont compares aux solutions approchees de l'equation de transport de Boltzmann. (author) [Spanish] Los autores han empleado un acelerador Van de Graafi, que emitia rafagas de neutrones pulsados del orden del nanosegundo, para estudiar el comportamiento de los neutrones rapidos en conjuntos de metales no multiplicadores. Emplearon esta tecnica de la fuente de neutrones pulsados a fin de medir las secciones eficaces de dispersion inelastica de los neutrones rapidos en el Fe. El metodo empleado es analogo al utilizado para medir las secciones eficaces de absorcion en conjuntos termicos, salvo el hecho de que los tiempos de decrecimiento de los neutrones rapidos son del orden del nanosegundo mas bien que del microsegundo. En estos experimentos, se inyectaron rafagas de neutrones monoenergeticos, del orden del nanosegundo, en conjuntos de Fe de diversas dimensiones. Se observo que, en esos conjuntos, el flujo neutronico decrece exponencialmente con una constante caracteristica. Esta constante de decrecimiento esta constituida por una suma de terminos que representan la perdida de neutrones debidos al escape y a la degradacion energetica. Esta ultima representa una perdida de neutrones toda vez que se emplea un detector neutronico polarizado. El termino de eliminacion correspondiente a la dispersion elastica e inelastica puede determinarse midiendo la constante de decrecimiento en funcion de las dimensiones del conjunto de que se trate. Los autores exponen un procedimiento teorico que permite calcular la medida en que la dispersion elastica contribuye al termino de eliminacion, con lo que puede calcularse subsiguientemente la seccion eficaz de dispersion inelastica. El procedimiento teorico se ha comprobado experimentalmente para calcular la contribucion de la dispersion elastica. Empleando esta tecnica, se ha medido la seccion eficaz de dispersion inelastica correspondiente al Fe, para energias de los neutrones primarios comprendidas entre 0,8-y 1,5 MeV. Esta tecnica de empleo de una fuente de neutrones pulsados se ha utilizado tambien para medir las constantes de decrecimiento en placas de Pb. Las condiciones de experimentacion se aproximan a los supuestos que suelen formularse cuando se resuelve la ecuacion de transporte de Boltzmann en funcion del tiempo (es decir, una sola dimension y una sola velocidad). Los autores han medido las constantes de decrecimiento en placas de plomo de 71 x 81 cm. con espesores de 5, 10, 15 y 20 cm, y comparan los resultados alcanzados, una vez corregidos para tener en cuenta la degradacion energetica y el conjunto finito,con las soluciones aproximadas de la ecuacion de transporte de Boltzmann. (author) [Russian] Uskoritel' Van-de-Graafa s nanosekundnymi impul'sami ispol'zovali dlja izuchenija povedenija bystryh nejtronov v nerazmnozhajushhih metallicheskih sborkah. Dlja izmerenija sechenij neuprugogo rassejanija zheleza na bystryh nejtronah primenili metod impul'snogo istochnika nejtronov, analogichnyj metodu, primenjaemomu dlja izmerenija sechenij pogloshhenija v teplovyh sborkah, za iskljucheniem togo, chto vremja bystrogo spada izmerjaetsja nano-, a ne mikrosekundami. Nanosekundnye impul'sy monojenergeticheskih nejtronov inzhektirujutsja v zheleznye sborki razlichnyh razmerov. Otmecheno, chto potok nejtronov v jetih sborkah spadaet jeksponencial'no s harakteristicheskoj postojannoj spada. Postojannaja spada sostoit iz summy chlenov, kotorye predstavljajut soboj poterju nejtronov vsledstvie utechki i poteri jenergii, poterja jenergii predstavljaet so''oj poterju nejtronov, poskol'ku ispol'zuetsja porogovyj nejtronnyj detektor. Chlen utechki za schet uprugogo i neuprugogo rassejanija mozhno opredelit' putem izmerenija postojannoj spada v zavisimosti ot razmera sborki. Predstavlen teoreticheskij vyvod dlja rascheta doli uprugogo rassejanija v chlene utechki i, sledovatel'no, mozhno opredelit' sechenie neuprugogo rassejanija. Teoreticheskaja traktovka dlja rascheta vklada uprugogo rassejanija proverena jeksperimental'nym putem. Sechenie neuprugogo rassejanija zheleza izmereno s pomoshh'ju jetogo metoda dlja pervichnoj jenergii nejtronov v diapazone 0,8 -1,5 Mjev. Vysheopisannyj metod impul'snogo istochnika nejtronov byl ispol'zovan dlja. izmere nija postojannoj spada v otnoshenii svincovyh plastin. Jeksperimental'nye dannye primerno soglasujutsja s predpolozhenijami, kotorye obychno delajut pri reshenii bol'cmanovskogo uravnenija perenosa s vremennoj zavisimost'ju (t.e. odnomernoe, odnoskorostnoe). Postojannye spada izmereny dlja svincovyh plastin razmerom 28x32 djujma i tolshhinoj 2; 4; b i 8 djujmov. Posle vnesenija popravki na poterju jenergii i konechnye razmery sborki rezul'taty sravnivajutsja s priblizitel'nymi reshenijami bol'cmanovskogo uravnenija perenosa. (author)

  15. A novel time-to-pulse height converter for fast-neutron time-of-flight techniques; Nouveau convertisseur temps-amplitude d'impulsions pour les mesures du temps de vol des neutrons rapides; Novyj vremya-amplitudnyj preobrazovatel' impul'sov dlya izmereniya vremeni proleta bystrykh nejtronov; Nuevo convertidor tiempo-altura de impulsos para tecnicas de tiempo de vuelo de neutrones rapidos

    Energy Technology Data Exchange (ETDEWEB)

    Christiansen, J [Physikalisches Staatsinstitut, Hamburg, Federal Republic of Germany (Germany)

    1962-04-15

    An electronic time-to-pulse height converter is described which uses a multiplicative method instead of the usual one of adding overlapping pulses. This is achieved by a coincidence of a linear sawtooth and a sharply clipped needle-pulse. The sawtooth is fed to the grid of a beam-deflecting tube (E80T) and the needle-pulse is applied to the deflecting plates and opens the tube only during a time-interval of about 5.10{sup -9} s. The plate gets a charge proportional to the time-difference between the start of the sawtooth and the needle pulse. The plate-pulse is stretched and amplified and its height represents a measurement of the time-difference. With this method we got a time resolution of 2{tau} = 7 x 10{sup -12}s with artificial pulses, 2{tau} = 3 x 10{sup -10}s with Co{sup 60} {gamma}-coincidences by using NE 102 plastic crystals and 2{tau} = 1.4 x 10{sup -9} s with 511-keV {gamma}-coincidences using NaI(Te) crystals. The method was also used with pulsed beam techniques. In this case we got from the pulsing RF an 8-Mc, sharply-peaked pulse-sequence, which was fed to the E80T plates. We had a time-resolution of 2{tau} = 1.1 x 10{sup -9} s with 4-MeV neutrons using plastic crystals 0.7 in long. Normally the region of linear response was 30 ns but it was possible to go up to 120 ns. (author) [French] L'auteur decrit un convertisseur electronique temps en amplitude d'impulsions fonctionnant d'apres une methode de multiplication au lieu de la methode habituelle qui consiste a ajouter des impulsions qui se chevauchent. On fait coincider une impulsion lineaire en dents de scie avec une impulsion en forme d'aiguille fortement ecretee. L'impulsion en dents de scie est envoyee sur la grille d'un tube a faisceaux electroniques diriges (E80T) ; et l'impulsion en forme d'aiguille est appliquee aux plaques de deflexion et n'ouvre le tube que pendant un intervalle de temps d'environ 5 {center_dot} 10{sup -9} s. La plaque recoit une charge proportionnelle a la difference de temps entre le demarrage de chacune des deux impulsions. L'impulsion de la plaque est etalee et amplifiee; son amplitude represente la mesure de la difference de temps. Avec cette methode l'auteur a obtenu un temps de resolution de 2{tau} = 7 {center_dot} 10{sup -12} s avec des impulsions artificielles de 2{tau} = 3 {center_dot} 10{sup -10} s, avec des coincidences gamma du {sup 60}Co, en utilisant des cristaux en plastique NE 102, et de 2{tau} = 1,4 {center_dot} 10{sup -9} s avec des coincidences gamma de 511 keV, en utilisant des cristaux de Nal (Te). Cette methode a ete egalement utilisee avec des faisceaux puises. Dans ce cas l'auteur a obtenu, a partir de la radiofrequence de pulsation, une suite d'impulsions de 8 Mc en pointes aigues, qui ont ete envoyees sur les plaques E80T. Le temps de resolution a ete de 2{tau} = 1,1 {center_dot} 10{sup -9} s avec des neutrons de 4 MeV, en utilisant des cristaux de plastique de 36 mm de long. Normalement la reponse lineaire se situe dans une region de 30 ns mais il est possible qu'elle atteigne 120 ns. (author) [Spanish] En la memoria se describe un convertidor electronico tiempo-altura de impulsos, en el que se aplica un metodo de multiplicacion, en vez del metodo habitual de suma de impulsos que se superponen. Esto se logra haciendo coincidir dos impulsos, uno lineal en diente de sierra y uno muy aguzado. El impulso en diente de sierra se transmite a la rejilla de una valvula de haz dirigido (E80T) y el impulso aguzado se aplica a las placas deflectoras, abriendo la valvula solo durante un intervalo de unos 5 {center_dot} 10{sup -9} s. La placa recibe una carga proporcional al periodo entre el comienzo del impulso en diente de sierra y el impulso aguzado. El impulso de la placa es alargado y amplificado y su altura representa una medicion de la diferencia de tiempos. Con este metodo se han obtenido tiempos de resolucion de 2{tau} = 7 {center_dot} 10{sup -12} s con impulsos artificiales, de 2{tau} = 3 {center_dot} 10{sup -10} s con coincidencias gamma obtenidas de una fuente de {sup 60}Co y utilizando cristales plasticos NE 102, y de 2{tau} = 1,4 {center_dot} 10{sup -9} con coincidencias gamma de 511 KeV y utilizando cristales de Nal (Te). El metodo se utilizo tambien aplicando tecnicas de haces pulsantes. En la experiencia realizada se obtuvo, a partir de una radiofrecuencia pulsadora, una sucesion de impulsos muy aguzados, con una frecuencia de 8 MHz, que se transmitio a las placas de la valvula E80T. Se obtuvo un tiempo de resolucion de 2{tau} = 1,1 {center_dot} 10{sup -9} s con neutrones de 4 MeV, utilizando cristales plasticos de 0,7 pulgadas de largo. Normalmente la region de respuesta lineal fue de 30 ns (30 {center_dot} 10{sup -9} s), pero se consiguio aumentarla hasta 120 ns. (author) [Russian] Opisyvaetsya ehlektronnyj vremya-amplitudnyj preobrazovatel' impul'sov s ispol'zovaniem metoda umnozheniya perekryvayushchikhsya impul'sov vmesto obychnogo metoda ikh slozheniya. EHto dostigaetsya polucheniem sovpadeniya linejnogo piloobraznogo impul'sa s rezko ogranichennym igol'chatym impul'som. Piloobraznyj impul's postupaet na reshetku otklonyayushchej puchok lampy (E80T), a igol'chatyj impul's napravlyaetsya na otklonyayushchie plastiny, gde on otkryvaet lampu tol'ko v techenie promezhutka vremeni priblizitel'no 5 x 10{sup -9} sekund. Plastina poluchaet zaryad, proportsional'nyj raznitse vo vremeni mezhdu nachalom piloobraznogo i nachalom igol'chatogo impul'sov. Posylaemyj plastinoj impul's rasshiryaetsya i usilivaetsya i amplituda ego sootvetstvuet velichine raznitsy vo vremeni. EHtim metodom udalos' poluchit' razreshayushchuyu sposobnost' po vremeni, ravnuyu {tau} = 7 x 10{sup -12} sekundam s iskusstvennymi impul'sami, {tau} = 3 x 10{sup -10} sekundam s sovpadeniyami dlya kobal'ta-60 pri ispol'zovanii plasticheskogo kristalla NE 102, i {tau} = 1,4 x 10{sup -9} sekundy pri sovpadeniyakh v 511 kehv pri ispol'zovanii kristallov Nal (Te). EHtot metod byl ispol'zovan takzhe v sochetanii s metodami pul'siruyushchego puchka. V ehtom sluchae iz pul'siruyushchej radiochastoty RF my poluchili potok impul'sov s ostrymi pikami v 8 Mc, kotoryj napravlyalsya na plastiny lampy E80T. My p o l u ch i li razreshayushchuyu sposobnost' po vremeni, ravnuyu {tau} = 1,1 x 10{sup -9} sekundy s nejtronami ehnergiej v 4 mehv pri ispol'zovanii plasticheskikh kristallov dlinoyu v 0,7 dyujma. Obychno zona linejnoj kharakteristiki poluchalas' na protyazhenii 30 nanosekund, no udavalos' dokhodit' i do 120 nanosekund. (author)

  16. The world’s first pelletized cold neutron moderator at a neutron scattering facility

    Energy Technology Data Exchange (ETDEWEB)

    Ananiev, V.; Belyakov, A.; Bulavin, M.; Kulagin, E.; Kulikov, S.; Mukhin, K.; Petukhova, T.; Sirotin, A.; Shabalin, D.; Shabalin, E.; Shirokov, V.; Verhoglyadov, A., E-mail: verhoglyadov_al@mail.ru

    2014-02-01

    In July 10, 2012 cold neutrons were generated for the first time with the unique pelletized cold neutron moderator CM-202 at the IBR-2M reactor. This new moderator system uses small spherical beads of a solid mixture of aromatic hydrocarbons (benzene derivatives) as the moderating material. Aromatic hydrocarbons are known as the most radiation-resistant hydrogenous substances and have properties to moderate slow neutrons effectively. Since the new moderator was put into routine operation in September 2013, the IBR-2 research reactor of the Frank Laboratory of Neutron Physics has consolidated its position among the world’s leading pulsed neutron sources for investigation of matter with neutron scattering methods.

  17. Radiation resistance of concrete of nuclear reactor vessel

    International Nuclear Information System (INIS)

    Belyakov, V.V.; Denisov, A.V.; Korenevskij, V.V.; Muzalevskij, L.P.; Dubrovskij, V.B.; Ivanov, D.A.; Nazarov, I.L.; Sashin, N.L.

    1992-01-01

    Results of calculational-experimental determination of radiation resistance for concrete bases on limestone gravel and quartz sand, which are the most perspective materials for manufacturing prestressed concrete of the VG-400 reactor vessel are considered. Material samples under investigation were irradiated in the channels of the IBR-2 research reactor for the purpose of the calcultional result verification

  18. International seminar on structural investigations on pulsed neutron sources. Proceedings

    International Nuclear Information System (INIS)

    Aksenov, V.L.; Balagurov, A.M.; Taran, Yu.V.

    1993-01-01

    The proceedings of the International seminar on structural investigations using pulsed neutron sources are presented. The seminar is dedicated to the memory of Dr. Yu.M. Ostanevich, a world acknowledged physicist. The problems of structural analysis using pulsed neutron source at the IBR-2 reactor are discussed

  19. Spectrometer for neutron inelastic scattering investigations of microsamples

    International Nuclear Information System (INIS)

    Balagurov, A.M.; Kozlenko, D.P.; Platonov, S.L.; Savenko, B.N.; Glazkov, V.P.; Krasnikov, Yu.M.; Naumov, I.V.; Pukhov, A.V.; Somenkov, V.A.; Syrykh, G.F.

    1997-01-01

    A new neutron spectrometer for investigation of inelastic neutron scattering on polycrystal microsamples under high pressure in sapphire and diamond anvils cells is described. The spectrometer is operating at the IBR-2 pulsed reactor in JINR. Parameters and methodical peculiarities of the spectrometer and the examples of experimental studies are given. (author)

  20. Cell culture adaptation mutations in foot-and-mouth disease virus serotype A capsid proteins: implications for receptor interactions

    Science.gov (United States)

    In this study we describe the adaptive changes fixed on the capsid of several foot-and-mouth disease virus serotype A strains during propagation in cell monolayers. Viruses passaged extensively in three cell lines (BHK-21, LFBK and IB-RS-2), consistently gained several positively charged amino acids...

  1. Resolution function in neutron diffractometry

    International Nuclear Information System (INIS)

    Popa, N.

    1987-01-01

    The resolution function in the neutron diffractometry is defined, on base of generalizing the resolution formerly formulated for the double axis neutron spectrometer. A polemical discussion is raised concerning an approach to this function existent in literature. The actual approach is concretized for the DN-2 time-of-flight diffractometer installed at the IBR-2 reactor

  2. The Enrico Fermi Atomic Power Plant; La centrais nucleaire Enrico Fermi; Atomnaya ehlektrostantsiya im Ehnriko Fermi.; La central nucleoelectrica Enrico Fermi

    Energy Technology Data Exchange (ETDEWEB)

    Hartwell, R. W. [Power Reactor Development Company, Detroit, MI (United States)

    1963-10-15

    rodean al reactor se habia deteriorado. Esos bloques para altas temperaturas estaban impregnados con boro; se habian dilatado y perdido resistencia. Un analisis detenido puso de manifiesto que el agente aglomerante del grafito habia cedido. Se decidio sustituir todo el grafito, utilizar carburo de boroen vez de boro, sujetar los bloques con dispositivos mecanicos y reducir al minimo la humedad. Modificaciones en el interior del recipiente del reactor. Se realizaron reparaciones y se introdujeron modificaciones en el diseflo a tin de evitar la adherencia de los subconjuntos y el dallo resultante, asi como para prevenir otras fallas del mecanismo de manejo de los elementos combustibles. Para ello, se desmonto el mencionado mecanismo y se extrajo el sodio del recipiente del reactor. Personal especializado que vestia trajes protectores especiales penetro en el interior del recipiente a traves de una esclusa neumatica especial, ya que en el interior del recipiente se mantenia una atmosfera de argon. Modificaciones en los generadores de vapor. Cuando se realizaron loe ensayos hidrostaticos del generador de vapor No. 2, se descubrieron fugas en varias tuberias. Las investigaciones subsiguientes pusieron de manifiesto que esa falla de las tuberias obedecia a un agrietamiento debido a la corrosion bajo tension. Se cambiaron las tuberias del generador No. 2, se eliminaron las tensiones de todas las unidades y se instalo un dispositivo detector de hidrogeno. En diciembre de 1962 el sodio reacciono con el agua en el generador de vapor No. 1. El disco de seguridad instalado en prevision de tal contingencia funciono correctamente. En la actualidad se estan investigando las causas y efectos de esa falla. Terminacion de los ensayos preliminares. A la espera de un permiso de explotacion a baja potencia, se esta terminando el montaje y el programa de ensayos (marzo de 1963). (author) [Russian] Stroitel'stvo atomnoj ehlektrostantsii im. Ehnriko Fermi s reaktorom-razmnozhitelem na bystrykh

  3. Evaluation of Dose: Comparative Effect of Fast Neutrons and other Types of Radiation on the Survival of E. Coli and S. Cerevisiae; Evaluation de la Dose Delivree et Actions Comparees des Neutrons Rapides et d'Autres Radiations sur la Survie de E. Coli et S. Cerevisiae; Otsenka dozy i sravnitel'noe vliyanie bystrykh nejtronov i drugikh vidov izlucheniya na vyzhivaemost' E. Coli i S. Cerevisiae; Evaluacion de la Dosis Suministrada y Comparacion de la Accion de los Neutrones Rapidos sobre la Supervivencia del E. Coli y del S. Cerevisiae con la de Otras Radiaciones

    Energy Technology Data Exchange (ETDEWEB)

    Arnaud, Y.; Bocquet, C. [Centre d' Etudes Nucleaires de Saclay (France)

    1964-05-15

    The EL-3 reactor is equipped with auranium converter by means of which fast neutrons can be obtained. A bank of fission chambers measures the flux and spectral distribution of the fast neutrons. These miniature detectors are placed at various points in the target zone and make possible the experimental evaluation of the absorbed tissue-dose. This apparatus and dosimetric technique can be used to compare the effect of fast neutrons and other types of ionizing radiation (e.g. X-rays) on unicellular organisms. The authors study the percentage of survivals and the frequency of a mutation in Saccharomyces cerevisiae. The survival curve for Escherichia coli is also determined for X-rays and neutrons. It is found that the RBE's of these various types of radiation depend not only on the species and the biological criterion adopted, but also on the irradiation dose-level at which the comparison is made. These experiments show the RBE to be also a function of dose. The effects of fast neutrons and X-rays are often brought about by differing radiobiological processes. It is arbitrary to establish linear relationships between the doses for these various types of radiation. (author) [French] Nous disposons aupres du reacteur EL3 d'un convertisseur a uranium permettant d'obtenir des neutrons rapides. Une batterie de chambres a fission mesure le flux et la repartition spectrale des neutrons rapides. Ces detecteurs miniatures sont places en divers points du volume a irradier et permettent d'evaluer experimentalement la dose absorbee dans les tissus. Ce dispositif et cette dosimetrie nous servent a comparer l'action des neutrons rapides et d'autres radiations ionisantes (X, {gamma}) sur des organismes monocellulaires. Nous etudions ici le pourcentage de survie et la frequence d'une mutation morphologique chez Saccharomyces cerevisiae. La courbe de survie d'Escherichia coli est aussi etablie pour les rayons X et les neutrons. On observe que les effets biologiques relatifs de ces diverses radiations dependent de l'organisme vivant etudie, du critere biologique choisi, mais aussi de la dose d'irradiation avec laquelle on fait la comparaison. L'efficacite biologique relative apparait dans ces experiences comme etant egalement une fonction de la dose. L'action des neutrons rapides et des rayons X releve souvent de processus radiobiologique differents. Il est arbitraire de relier entre elles les doses de ces diverses radiations par des relations lineaires. (author) [Spanish] Junto al reactor EL3 se encuentra un convertidor de uranio que permite obtener neutrones rapidos. Con una bateria de camaras de fision se mide el flujo y la distribucion espectral de los neutrones rapidos. Estos micro- detectores estan colocados en diversos puntos del volumen que se ha de irradiar y permiten evaluar experimentalmente la dosis absorbida en los tejidos. Gracias a este dispositivo y a este sistema de dosimetria, los autores han podido comparar la accion de los neutrones rapidos con las de otras radiaciones ionizantes (rayos X, rayos y) sobre organismos unicelulares. En este trabajo, estudian el porcentaje de supervivencia y la frecuencia de una mutacion morfologica en el Saccharomyces cerevisiae. Tambien han trazado la curva de supervivencia del Escherichia coli, expuesto a rayos X y a neutrones. La observacion de los resultados indica que los efectos biologicos relativos de estas diversas radiaciones dependen del organismo vivo estudiado, del criterio biologico elegido y, ademas, de la dosis de irradiacion con que se realiza la comparacion. Tambien se deduce de estos experimentos que la eficacia biologica relativa es funcion de la dosis. A menudo, la accion de los neutrones rapidos y de los rayos X depende de diferentes procesos radiobiologicos. Seria arbitrario establecer relaciones lineales entre las dosis de dichas radiaciones. (author) [Russian] Na reaktore EL-3 imeetsja uranovyj preobrazovatel, pozvoljajushhij poluchat' bystrye nejtrony. Batareja kamer delenija proizvodit izmerenie potoka i spektral'nogo raspredelenija bystryh nejtronov. Jeti miniatjurnye detektory razmeshhajutsja v razlichnyh tochkah obluchaemogo obrazca i pozvoljajut jeksperimental'no ocenivat' pogloshhaemuju tkanjami dozu. Takaja ustanovka i dozimetrija dali vozmozhnost' sravnit' vlijanie bystryh nejtronov i drugih vidov ionizirujushhego izluchenija (rentgenovy luchi) na odnokletochnye organizmy. Izuchalsja procent vyzhivaemosti i chastota morfologicheskih mutacij u Saccharo- myces cerevisiae. Ustanovlena takzhe krivaja vyzhivaemosti Escherichia coli v otnoshenii rentgenovyh luchej i nejtronov. Otmechaetsja, chto OBJe jetih razlichnyh vidov izluchenija zavisit ot issleduemogo zhivogo organizma, ot izbrannogo biologicheskogo kriterija, a takzhe ot dozy obluchenija, pri kotoroj proizvoditsja sravnenie. V jetih uslovijah OBJe javljaetsja funkciej dozy. Dejstvie bystryh nejtronov i rentgenovyh luchej chasto zavisit ot razlichnyh radiobiologicheskih processov. Bylo by proizvol'no svjazyvat' mezhdu soboj dozy jetih razlichnyh izluchenij linejnymi otnoshenijami. (author)

  4. Relative Biological Effectiveness of 14-MeV Fast Neutrons to Co{sup 60} Gamma-Rays in Einkorn Wheat; Efficacite Biologique Relative des Neutrons Rapides de 14 MeV par Rapport aux Rayons Gamma de {sup 60}Co sur l'Engrain; Otnositel'naya biologicheskaya ehffektivnost' bystrykh nejtronov s ehnergiej 14 MeV i gamma-luchej CO{sup 60} pri ikh dejstvii na pshenitsu odnozernyanku; EBR de los Neutrones Rapidos de 14 MeV y de los Rayos Gamma del {sup 60}Co en el Trigo Escanda Menor

    Energy Technology Data Exchange (ETDEWEB)

    Fujii, T. [National Institute of Genetics, Misima (Japan)

    1964-05-15

    The author investigated the RBE of 14 MeV neutrons to Co{sup 60} gamma-rays by using the specific locus method in Einkorn wheat. F{sub 1} seeds from the cross between the original strain and a chlorina mutant were used in this study (chlorina mutant was obtained as a single recessive mutant from X-irradiation; it was uniformly light green from seedling stage to maturity with relatively high survival rate and fertility). The F{sub 1} plants showed normal green colour and normal growth habit. Dormant F{sub 1} seeds were irradiated at 0.5 , 1.0 and 1.4 krad of fast neutrons ami 4.3 , 8.6 and 12.9 krad of gamma-rays. Mutations from dominant normal green to chlorina occurred by both irradiations and appeared in the leaves and stems of the heterozygotic Xi plants as longitudinal stripes. Around 80% of seeds germinated in the control lot and in the lowest dosage lots from both neutron and gamma-ray irradiations, and germination percentages were gradually decreased with increasing dosage of both kinds of radiation. Moreover, a similar tendency was observed at the early stage as to seedling growth which was gradually inhibited with increasing dosage. According to these results, neutron irradiation was about 13 times more effective than that of gamma-rays. Survival rate in the non-irradiated control was about 90% and about 60-80% of germinated seedlings survived in 0.5 and 1.0 krad lots from neutron irradiation and all lots irradiated by gamma-rays. On the other hand, only about 4% of germinated seedlings survived in the highest neutron lot. No mutation was observed in the control lot, and the number of plants which contained striped tillers increased with increasing dosage of both kinds of radiation. Mutated tillers were observed in about 15% of surviving plants obtained at the lowest dosage of neutron irradiation and a similar frequency was observed from the highest dosage of gamma-rays. RBE of 14 MeV neutrons to Co{sup 60} gamma-rays seemed to be at least 20 for the somatic mutation. (author) [French] L' auteur a etudie l'EBR des neutrons de 14 MeV par rapport aux rayons gamma de {sup 60}Co en appliquant a l'engrain la methode des loci specifiques. Il a utilise pour cette etude des semences Fi resultant du croisement entre l'espece originale et un mutant chlorina (le mutant chlorina e ta it le produit d'une mutation recessive induite par les rayons X ; depuis le stade de plantule jusqu'a sa maturite, le m utant a conserve une couleur vert c la ir uniforme ainsi qu'un taux de survie et une fe rtilite relativement eleves). Les plantes Fi avaient une couleur verte et une croissance normales. Des semences dormantes de F{sub 1} ont e te irradiees avec 0,5 , 1,0 et 1,4 krad de neutrons rapides et avec 4,3 , 8,6 et 12,9 krad de rayons gamma. Sous l'effet des deux types de rayonnements, il s'est produit des mutations de vert normal dominant en chlorina, sous forme de bandes longitudinales. Sur les feuilles et les tiges des heterozygotes X{sub 1}. Environ 80% des semences ont germe dans le lot temoin ainsi que dans les deux lots ayant recu la plus faible dose de neutrons et de rayons gamma; les taux de germination ont diminue a mesure qu'augmentaient les doses de neutrons et de rayons gamma. En outre, on a observe un phenomene analogue au debut de lacroissance de la plantule, qui etait progressivement inhibee a mesure qu'augmentait la dose de rayonnement. Les resultats obtenus montrent que l'irradiation par les neutrons est environ 13 fois plus efficace que celle par les rayons gamma. Le taux de survie des semences non irradiees du lo t temoin a e te de 90% environ; 60 a 80% des plantules ont survecu aux doses de 0,5 et 1,0 krad de neutrons; toutes les plantilles irradiees par les rayons gamma ont survecu. En revanche, 4% seulement des plantules ont survecu a 1,4 krad de neutrons. L'auteur n 'a pas observe de mutations chez les plantes du lo t temoin; le nombre des plantes a talles rayees a augmente en meme temps que les doses des deux types de rayonnements. E a observe des talles mutants dans pres de 15% des plantes qui ont survecu a la plus faible dose de neutrons et a constate que la frequence e ta it la meme pour les plantes qui avaient recu la dose la plus elevee des rayons gamma. L'EBR des neutrons de 14 MeV par rapport aux rayons gamma de {sup 60}Co semble etre d'au moins 20 pour la mutation somatique. (author) [Spanish] El autor estudio la EBR de los neutrones de 14 MeV con respecto a los rayos gamma del {sup 60}Co por el metodo del locus especifico en el trigo escanda menor. Empleo semillas Fi obtenidas por cruza entre la cepa original y el mutante chlorina (este ultimo se obtuvo como mutante recesivo unico por exposicion a los rayos X; conserva un color verde palido desde que germina hasta que alcanza la madurez, con indices de supervivencia y fertilidad relativamente elevados). Las plantas Fj presentan el color verde normal y tambien es normal la modalidad de desarrollo. El autor irradio las semillas de Fx latentes con neutrones rapidos (en dosis de 0,5 - 1,0 y 1,4 krad) y con rayos gamma (4 ,3 - 8,6 y 12,9 krad). Ambas radiaciones provocaron mutaciones del verde normal dominante al tono chlorina, que aparecio en las hojas y tallos de las plantas heterocigoticas en forma de rayas longitudinales. Alrededor del 80% de las semillas germino en el grupo testigo y en los grupos expuestos a los neutrones y rayos gamma en dosis bajas, pero el porcentaje de semillas germinadas fue decreciendo gradualmente a medida que aumentaba la dosis de ambos tipos de radiacion. Ademas, se observo una tendencia similar en la primera fase d el desarrollo de la plantula, que se inhibe paulatinamente al aumentar la dosis. De acuerdo con estos resultados, la irradiacion neutronica Inverted-Question-Mark s unas 13 veces mas eficaz que los rayos gamma. El in d ic e de supervivencia en el grupo testigo, no irradiado, fue del orden de 90%; en los grupos expuestos a los neutrones a razon de dosis de 0,5 y 1,0 krad, sobrevivio entre 60 y 80% de las plantulas y en los grupos tratados con rayos gamma, la supervivencia fue del 100%. En cambio, en el grupo sometido a la irradiacion neutronica con la dosis mas elevada, solo sobrevivio un 4% de las plantulas. No se observaron mutaciones en el grupo testigo y el numero de plantas que presentaba retonos rayados crecio al aumentar la dosis de ambos tipos de radiacion. Se observaron retoflos con mutaciones en un 15% de las plantas sobrevivientes tratadas con la dosis inferior de neutrones y la misma frecuencia se registro para la dceis mayor de rayos gamma. Al parecer, la EBR de los neutrones de 14 MeV con respecto a los rayos gamma de {sup 60}Co, para la mutacion somatica, es 20 como minimo. (author) [Russian] Avtor izuchal OBJe nejtronov s jenergiej 14 Mjev i gamma-luchej Sobo pri ih dejstvii na pshenicu odnozernjanku s pomoshh'ju special'nogo lokusnogo metoda. Dlja opyta ispol'zovalis' semena generacii F{sub 1} gibrida mezhdu ishodnym sortom i mutantom Chlorina (mutant Chlorina byl poluchen kak edinstvennyj recessivnyj rentgenomutant; ot stadii sejanca do nastuplenija spelosti on byl odnorodno svetlozelenym s otnositel'no vysokoj vyzhivaemost'ju i urozhajnost'ju). U rastenij F{sub 1} byla normal'naja zelenaja okraska i normal'nyj harakter rosta. Pokojashhiesja semena Ft obluchali bystrymi nejtronami v dozah 0,5, 1,0 i 1,4 krad i gamma-luchami v dozah 4,3 8,6 i 12,9 krad. Mutacii ot dominantnyh normal'nyh zelenyh do Chlorina nabljudalis' posle oboih vidov obluchenija i pojavljalis' v list'jah i stebljah geterozigotnyh rastenij X{sub 1} v vide prodol'nyh polos. Okolo 80% semjan vzoshlo na kontrol'nyh uchastkah i na uchastkah posle obluchenija ca- mymi nizkimi dozami nejtronov i gamma-luchej, procent vshozhesti postepenno snizhalsja s povysheniem dozy pri oboih vidah obluchenija. Krome togo, takaja zhe tendencija nabljudalas' i na rannih stadijah rosta sejancev, kotoryj postepenno tormozilsja s povysheniem dozy. Soglasno jetim dannym nejtronnoe obluchenie okazalos' pochti v 13 raz jeffektivnee gamma- luchej. Vyzhivaemost' neobluchennyh kontrol'nyh rastenij byla okolo 90%, a u prorosshih semjan na uchastkah posle obluchenija 0,5 i 1,0 krad nejtronov, i na vseh uchastkah posle gamma- obluchenija vyzhivaemost' sostavljala 60-80%. I, naprotiv, lish' okolo 4% prorosshih semjan vyzhili na uchastkah posle obluchenija samymi vysokimi dozami nejtronov. Na kontrol'nom uchastke mutacij ne obnaruzheno, a chislo rastenij s polosatymi pobegami vozrastalo s povysheniem dozy pri oboih bilah obluchenija. Mutantnye pobegi nabljudalis' primerno u 15% vyzhivshih rastenij, poluchivshih samye nizkie dozy nejtronnogo obluchenija, i u takogo zhe kolichestva rastenij, poluchivshih samye vysokie dozy gamma-obluchenija. OBJe nejtronov s jenergiej 14 Mjev po sravneniju s gamma-luchami Cot; v otnoshenii somaticheskih mutacij ravnjalos' po krajnej mere 20. (author)

  5. Improved Techniques for Low-Flux Measurement of Prompt Neutron Lifetime, Conversion Ratio and Fast Spectra; Methodes Perfectionnees de Mesure de la Duree de Vie des Neutrons Instantanes, du Rapport de Conversion et des Spectres de Neutrons Rapides, dans un Reacteur a Bas Flux; Usovershenstvovannye metody izmereniya vremeni zhizni mgnovennykh nejtronov, koehffitsienta konversii i spektra bystrykh nejtronov pri slabykh potokakh nejtronov; Tecnicas Perfeccionadas para la Determinacion del Periodo de los Neutrones Inmediatos, la Razon de Conversion y los Espectros de Neutrones Rapidos, con Flujos Reducidos

    Energy Technology Data Exchange (ETDEWEB)

    Armani, R. J.; Bennett, E. F.; Brenner, M. W.; Bretscher, M. M.; Cohn, C. E.; Huber, R. J.; Kaufmann, S. G.; Redman, W. C. [Argonne National Laboratory, Argonne, IL (United States)

    1964-02-15

    Various statistical methods for the measurement of the ratio of prompt neutron lifetime to delayed fraction have been used in the zero-power reactor programme. One method was originated here, i.e. analysis of reactor noise with a bandpass filter, and others such as the measurement of the frequency of delayed coincidences among counter pulses as a function of delay time and the measurement of the relative variance of time integrals of the neutron flux as a function of integrating time have been refined. The areas of most advantageous application of the various methods have been studied. Attention has also been given to the interpretation of the results of these measurements, and it has been shown that interpretation based on a simple kinetics model is applicable to a wide range of practical cases. Several improvements in our original activation method for the low flux determination of the ratio of production to destruction of fissile material are described. These include the application of very sensitive radiochemical techniques as a confirming procedure; correction for extraneous counts, utilizing foils of different enrichments for the contribution of fission of the fertile material to the fission- product activity and foils exposed to different spectra for fission-related counts in the capture determination; and the use of coincidence counting for the detection of Np{sup 239} decay. Obtaining a value for conversion ratio from the activation data requires a knowledge of the ratio of captures to fissions in the fuel, {alpha}. No accurate experimental method now exists for the measurement of this quantity in a low flux reactor, but several methods which might make feasible such a determination are being explored. Three of the more promising techniques are outlined. Efforts to develop a small fast neutron spectrometer of good stability, resolution and sensitivity for in-pile measurements of neutron spectra in the energy region of tens and hundreds of kilovolts have been concentrated on the use of pulse shape analysis to reject gamma-ray initiated events in hydrogen recoil proportional counters and the introduction of collimation in Li{sup 6}F solid-state detector ''sandwiches'' to improve the resolution obtained. A number of such instruments have been built and their response to mono-kinetic and reactor neutrons has been investigated. Use of the gamma-ray rejection technique was equivalent to a several hundred-fold effective reduction in gamma-ray sensitivity of the recoil counter and extends the usable range down to at least 30 keV. For the Li{sup 6} solid-state devices, resolutions as low as 70 keV full-width at half maximum (1.5%) have been observed for the sum pulse in thermal neutron irradiation. (author) [French] Dans le programme des reacteurs de puissance zero, on a utilise diverses methodes statistiques pour mesurer le rapport duree de vie des neutrons instantanes/duree de vie des neutrons differes. Les auteurs ont mis au point une methode nouvelle, qui consiste a analyser le bruit du reacteur a l'aide d'un filtre passe-bande, et ont perfectionne d'autres methodes telles que la mesure, a l'aide d'un compteur a impulsions, de la frequence des coincidences retardees en fonction du temps de retard et celle de la variance relative des flux de neutrons integres en fonction du temps d'integration. Ils ont etudie les domaines dans lesquels les differentes methodes peuvent etre utilisees avec le plus d'interet. II se sont aussi preoccupes de l'interpretation des resultats de ces mesures, et montrent que l'interpretation fondee sur un modele cinetique simple peut s'appliquer dans la pratique a une grande diversite de cas. Les auteurs decrivent plusieurs perfectionnements de leur methode d'activation pour la determination du rapport de conversion: application de techniques chimiques tres sensibles pour confirmer les resultats obtenus; correction pour les coups parasites en utilisant, dans la determination de la capture, des feuilles d'enrichissements differents pour etablir la contribution des fissions dans la matiere fertile a l'activite des produits de fission et des feuilles exposees a differents'spectres pour distinguer les coups dus a des fissions dans la determination des captures; emploi du comptage par coiencidence pour la detection de la decroissance de {sup 239}Np. Pour obtenir une valeur exprimant le rapport de conversion, a partir des donnees relatives a l'activation, il faut connaitre le rapport entre les captures et les fissions dans le combustible. Il n'existe pas a l'heure actuelle de methodes experimentales precises pour mesurer ce rapport dans un reacteur a bas flux; plusieurs methodes qui pourraient etre utilisees a cette fin sont en cours d'etude. Les auteurs decrivent trois des methodes qui offrent les perspectives les plus favorables. Pour construire un petit spectrometre a neutrons rapides, ayant une bonne stabilite, un bon pouvoir de resolution et une bonne sensibilite en vue de la mesure en pile des spectres neutroniques compris dans la gamme d'energies des dizaines et des centaines de kV, les auteurs ont concentre leurs efforts sur l'utilisation de l'analyse de la forme des impulsions - afin d'eliminer les evenements produits par les rayons gamma dans les compteurs proportionnels fondes sur des protons de recul de l'hydrogene - et sur l'introduction de la collimation dans les 'sandwiches' {sup 6}LiF-semi-conducteurs - afin d'augmenter le pouvoir de resolution. Ils ont construit un certain nombre de ces appareils et etudie leur reponse aux neutrons monocinetiques et aux neutrons produits dans un reacteur. En utilisant la technique d'elimination des rayons gamma, ils ont pu reduire de plusieurs centaines de fois la sensibilite du compteur de recul aux rayons gamma et de cette maniere abaisser la limite inferieure d'application de l'instrument a 30 keV. Pour les appareils {sup 6}Li-semi-conducteurs, ils ont observe des pouvoirs de resolution de 70 keV ( largeur entiere a mi- hauteur 1,5%), pour la somme des impulsions dans l'irradiation par les neutrons thermiques. (author) [Spanish] En el programa del reactor ZPR, se han aplicado varios metodos estadfsticos para determinar la razon perfodo de los neutrones inmediatos/perfodo de la fraccion de neutrones retardados. Los autores idearon uno de los metodos, consistente en el analisis del ruido del reactor con un filtro de paso de banda, y perfeccionaron otros, taies como la medicion de la frecuencia de coincidencias retardadas entre los impulsos del contador en funcion del retardo, y la determinacion de la variancia relativa de las integrales de tiempo del flu jo neutronico en funcion del tiempo de integracion. Han estudiado en que terrenos se aplican mas ventajosamente los distintos metodos. Tambien han procurado interpretar los resultados de las mediciones precitadas y han comprobado que la interpretacion basada en un modelo cinetico simple puede aplicarse a numerosos casos practicos. Los autores describen varios perfeccionamientos introducidos en su metodo original de activacion para la determinacion de la razon produccion/destruccion de material fisionable, con flujos reducidos. Entre ellos figuran la aplicacion de tecnicas radioqufmicas de alta sensibilidad como procedimiento de confirmacion; la correccion de impulsos parasitos, mediante laminas de diferente grado de enriquecimiento, para determinar la contribucion de la fision del material fertii a la actividad de los productos de fision, asi como Iaminas expuestas a los diferentes espectros para medir los impulsos relacionados con los sucesos de fision en la determinacion de la captura; y en el empleo del recuento por coincidencias para la deteccion de la desintegracion del {sup 239}Np. Para deducir la razon de conversion partiendo de los datos relativos a la activacion, es preciso conocer el coeficiente {alpha}, es decir, la razon capturas/fisiones en el combustible. Por ahora no existe ninguen metodo experimental que permita medir este valor en un reactor de flujo reducido, pero se estan estudiando algunos que pueden servir a ese fin. Los autores resefian tres de las tecnicas que ofrecen mejores perspectivas. Los estudios realizados con el proposito de construit un espectrometro pequeflo para neutrones rapidos con buenas caracteristicas de estabilidad, poder de resolucion y sensibilidad, destinado a la medicion de espectros neutronicos dentro del reactor, en el intervalo energetico de las decenas o centenares de kilovoltios, se han concentrado en el empleo del analisis de la forma de los impulsos (con el fin de rechazar los sucesos iniciados por los rayos gamma en los contadores proporcionales de retroceso de hidtogeno) y el empleo de la colimacion en los detectores tipo sandwich, a base de {sup 6}LiF en un material solido, a fin de aumentar el poder de resolucion. Se ha construido cierto ndmero de instrumentes de este tipo y se esta estudiando la forma en que se comportan frente a los neutrones monocineticos y los neutrones de un reactor. Recurriendo a la tecnica de rechazo de los rayos gamma, se ha podido reducir varios cientos de veces la sensibilidad del contador de retroceso frente a dichos rayos y de esta manera, el limite inferior de aplicacion del instrumente se ha extendido por lo menos hasta los 30 keV. En cuanto a los instrumentes de semiconductors a base de {sup 6}Li, se han observado poderes de resolucion de hasta 70 keV de amplitud total en correspondencia con la mitad del maximo (1,5%) para la suma de los impulsos, en la irradiaeion con neutrones termicos. (author) [Russian] Pri osushhestvlenii programmy issledovanija reak- tora nulevoj moshhnosti (ZPR) primenjalis' razlichnye statisticheskie metody izmerenija ot- noshenija vremeni zhizni mgnovennyh nejtronov k doze zapazdyvajushhih nejtronov. Odin metod, a imenno analiz ''shuma'' reaktora s pomoshh'ju polosovogo fil'tra byl razrabotan v laboratorii, a drugie, naprimer izmerenie chastoty zapazdyvajushhih sovpadenij impul'sov schet- chika kak funkcii vremeni zapazdyvanija i izmerenie otnositel'nogo otklonenija integralov vo vremeni potoka nejtronov kak funkcii integriruemogo vremeni, byli uluchsheny. Izu- cheny oblasti naibolee uspeshnogo primenenija razlichnyh metodov. Bylo udeleno takzhe vni- manie interpretacii rezul'tatov jetih izmenenij, i bylo pokazano, chto interpretacija na osnove prostoj kineticheskoj modeli primenima dlja shirokogo kruga konkretnyh sluchaev. Opisyvajutsja neskol'ko usovershenstvovanij nashego pervonachal'nogo aktivacionnogo metoda opredelenija otnoshenija obrazovanija k razrusheniju deljashhegosja veshhestva pri slabyh potokah nejtronov. Sjuda vhodit primenenie ochen' chuvstvitel'nyh radiohimicheskih metodov dlja proverki poluchennyh rezul'tatov; vnesenie popravok s cel'ju ucheta pomeh; primenenie fol'g razlichnoj stepeni obogashhenija dlja dobavlenija aktivnosti deljashhegosja materiala k aktivnosti produktov delenija; primenenie fol'g. obluchennyh nejtronami razlichnyh jenergij, dlja scheta delenij pri opredelenii zahvata; i ispol'zovanie scheta sovpadenij dlja obnaruzhenija raspada Np{sup 239}. Dlja poluchenija znachenija kojefficienta konversii po dannym aktivacii ne- obhodimo znat' otnoshenie kolichestva zahvatov k kolichestvu aktov delenija v toplive ({alpha}). V nastojashhee vremja ne sushhestvuet tochnogo jeksperimental'nogo metoda dlja izmerenija jetoj velichiny v reaktore so slabym potokom nejtronov; issledujutsja neskol'ko metodov, koto- rye, vozmozhno, pozvoljat opredelit' jetu velichinu. Opisyvajutsja dva ili tri perspektivnyh metoda. Usilija po sozdaniju nebol'shogo spektrometra bystryh nejtronov, imejushhego horoshuju stabil'nost', razreshajushhuju sposobnost' i chuvstvitel'nost' dlja izmerenija v reaktore spekt- ra nejtronov v oblasti jenegrii v desjatki i sotni kilovol't, byli sosredotocheny na prime- nenii analiza formy impul'sov dlja iskljuchenija vyzyvaemyh gamma-luchami javlenij v vodo- rodnyh proporcional'nyh schetchikah otdachi i na primenenii kollimirovanija v sloistyh konstrukcijah Li{sup 6}F-tverdyj detektor dlja povyshenija poluchennoj razreshajushhej sposobnosti. Rjad takih priborov byl postroen, i byla issledovana ih reakcija na monokineticheskie nej- trony i nejtrony, obrazujushhiesja v reaktore. Primenenie metoda iskljuchenija, vyzyvaemyh gamma-luchami javlenij, ravnosil'no jeffektivnomu snizheniju v neskol'ko sot raz chuvstvi- tel'nosti schetchika nejtronov otdachi k gamma-izlucheniju i rasshirjaet diapazon ego primenenija po krajnej mere do 30 kjev. Dlja ustrojstv Li{sup 6} -tverdyj detektor otmechena takaja niz- kaja razreshajushhaja sposobnost', kak 70 kjev ( polnaja shirina na polovine vysoty (1,5%) dlja summarnogo impul'sa pri obluchenii teplovymi nejtronami. (author)

  6. Automation of reactor neutron activation analysis

    International Nuclear Information System (INIS)

    Pavlov, S.S.; Dmitriev, A.Yu.; Frontasyeva, M.V.

    2013-01-01

    The present status of the development of a software package designed for automation of NAA at the IBR-2 reactor of FLNP, JINR, Dubna, is reported. Following decisions adopted at the CRP Meeting in Delft, August 27-31, 2012, the missing tool - a sample changer - will be installed for NAA in compliance with the peculiar features of the radioanalytical laboratory REGATA at the IBR-2 reactor. The details of the design are presented. The software for operation with the sample changer consists of two parts. The first part is a user interface and the second one is a program to control the sample changer. The second part will be developed after installing the tool.

  7. NAA for applied investigations at FLNP JINR. Present and future

    International Nuclear Information System (INIS)

    Frontasyeva, M.V.; Pavlov, S.S.; Shvetsov, V.N.

    2010-01-01

    Experience in applying conventional and epithermal neutron activation analysis for some challenging areas of life sciences and material science is reviewed. For more than 30 years of its operation the radioanalytical complex REGATA at the IBR-2 reactor in Dubna has become a source of analytical data for the environmental studies, marine geology, biotechnology and medicine, technological process of diamond and boron nitride synthesis, archaeology, nanomaterials, etc. In spite of competing non-nuclear analytical techniques (AAS, ICP-ES, ICP-MS, etc.), the reactor neutron activation analysis (NAA) as a primary (ratio) method continues to be the most powerful multielement analytical technique providing quantification of trace elements at ultralow levels. Combined with modern statistical data treatment of large arrays of data, GIS (geographic information system) technologies, electron scanning microscopy, tomography, and others, NAA serves to obtain actual, practical results resumed in the review. The perspectives of using the upgraded reactor IBR-2M for analytical investigations are discussed. (author)

  8. A study of formation of iron nanoparticles in aluminium matrix with helium pores

    Czech Academy of Sciences Publication Activity Database

    Kichanov, S.E.; Kozlenko, D. P.; Belushkin, A.V.; Reutov, V.F.; Samoilenko, S.O.; Jirák, Zdeněk; Savenko, B. N.; Bulavin, L. A.; Zubavichus, Y.V.

    2012-01-01

    Roč. 351, č. 1 (2012), "012013-1"-"012013-5" ISSN 1742-6588. [International Workshop on SANS-YuMO User Meeting at the Start-up of Scientific Experiments on the IBR-2M Reactor - Devoted to the 75th anniversary of Yu M Ostanevich's Birth /2./. Dubna, 27.05.2011-30.05.2011] Institutional research plan: CEZ:AV0Z10100521 Keywords : iron nanoparticles * aluminium matrix * helium pores Subject RIV: BM - Solid Matter Physics ; Magnetism

  9. The Model of Temperature Dynamics of Pulsed Fuel Assembly

    CERN Document Server

    Bondarchenko, E A; Popov, A K

    2002-01-01

    Heat exchange process differential equations are considered for a subcritical fuel assembly with an injector. The equations are obtained by means of the use of the Hermit polynomial. The model is created for modelling of temperature transitional processes. The parameters and dynamics are estimated for hypothetical fuel assembly consisting of real mountings: the powerful proton accelerator and the reactor IBR-2 core at its subcritica l state.

  10. Reconciling Through Science Exhibition Science Bringing Nations Together

    CERN Multimedia

    2000-01-01

    Over 200 experiments are carried out now with the pulsed neutron reactor IBR-2. They involve physicists, biologists and chemists from the scientific centres of the JINR Member States and other countries. Major contributions are made by the physicists from Germany, Hungary, Poland, and Russia. During a visit to Dubna, Niels Bohr took an interest in a simple idea behind the periodic pulsed reactor and said: "I admire the courage of the people who ventured to build such a remarkable facility!"

  11. Pattern recognition application for surveillance of abnormal conditions in a nuclear reactor

    International Nuclear Information System (INIS)

    Pepelyshev, Yu.N.; Dzwinel, W.

    1990-01-01

    The system to monitor abnormal conditions in a nuclear reactor, based on the noise analysis of the reactor basic parameters such as power, temperature and coolant flow rate, has been developed. The pattern recognition techniques such as clustering, cluster analysis, feature selection and clusters visualization methods form the basis of the software. Apart from non-hierarchical clustering procedures applied earlier, the hierarchical one is recommended. The system application for IBR-2 Dubna reactor diagnostics is shown. 10 refs.; 6 figs

  12. Small-angle neutron scattering investigations of Co-doped iron oxide nanoparticles. Preliminary results

    Science.gov (United States)

    Creanga, Dorina; Balasoiu, Maria; Soloviov, Dmitro; Balasoiu-Gaina, Alexandra-Maria; Puscasu, Emil; Lupu, Nicoleta; Stan, Cristina

    2018-03-01

    Preliminary small-angle neutron scattering investigations on aqueous suspensions of several cobalt doped ferrites (CoxFe3-xO4, x=0; 0.5; 1) nanoparticles prepared by chemical co-precipitation method, are reported. The measurements were accomplished at the YuMO instrument in function at the IBR-2 reactor. Results of intermediary data treatment are presented and discussed.

  13. Scattering and depolarization of polarized neutrons in ferrofluids

    International Nuclear Information System (INIS)

    Balasoiu, M.; Dokukin, E.B.; Kozhevnikov, S.V.; Nikitenko, Y.V.

    1999-01-01

    On the SPN - 1 polarized neutron spectrometer at IBR -2 high - flux pulsed rector there were carried out preliminary measurements on transmission and polarization of a neutron beam passing through a magnetic colloidal system of Fe 3 O 4 particles in transformer oil and dodecane carriers. It was found that in the ferrofluids with magnetite particles exist, dependent on the particle volume concentration and the magnitude of the external magnetic field, effects of depolarization and nuclear - magnetic small angle scattering. (author)

  14. Polarized neutron spectrometer

    International Nuclear Information System (INIS)

    Abov, Yu.G.; Novitskij, V.V.; Alfimenkov, V.P.; Galinskij, E.M.; Mareev, Yu.D.; Pikel'ner, L.B.; Chernikov, A.N.; Lason', L.; Tsulaya, V.M.; Tsulaya, M.I.

    2000-01-01

    The polarized neutron spectrometer, intended for studying the interaction of polarized neutrons with nuclei and condensed media in the area of energies from thermal up to several electron-volt, is developed at the IBR-2 reactor (JINR, Dubna). Diffraction on the Co(92%)-Fe(8%) magnetized monocrystals is used for the neutron polarization and polarization analysis. The neutron polarization within the whole energy range equals ∼ 95% [ru

  15. Irradiation tests of readout chain components of the ATLAS liquid argon calorimeters

    CERN Document Server

    Leroy, C; Golikov, V; Golubyh, S M; Kukhtin, V; Kulagin, E; Luschikov, V; Minashkin, V F; Shalyugin, A N

    1999-01-01

    Various readout chain components of the ATLAS liquid argon calorimeters have been exposed to high neutron fluences and $gamma$-doses at the irradiation test facility of the IBR-2 reactor of JINR, Dubna. Results of the capacitance and impedance measurements of coaxial cables are presented. Results of peeling tests of PC board samples (kapton and copper strips) as a measure of the bonding agent irradiation hardness are also reported.

  16. Irradiation tests of readout chain components of the ATLAS liquid argon calorimeters

    International Nuclear Information System (INIS)

    Leroy, C.; Cheplakov, A.; Golikov, V.; Golubykh, S.; Kukhtin, V.; Kulagin, E.; Lushchikov, V.; Minashkin, V.; Shalyugin, A.

    2000-01-01

    Various readout chain components of the ATLAS liquid argon calorimeters have been exposed to high neutron fluences and γ doses at the irradiation test facility of the IBR-2 reactor of JINR, Dubna. Results of the capacitance and impedance measurements of coaxial cables are presented. Results of peeling tests of PC board samples (carton and copper strips) as a measure of the bonding agent irradiation hardness are also reported

  17. A 15-year forward look at neutron facilities in JINR

    International Nuclear Information System (INIS)

    Aksenov, V.L.

    2017-01-01

    The service life of the IBR-2 reactor, one of the leading pulse neutron sources in the world, is expected to end in 2032. Modern trends in sciences where neutrons are used, possible variants of a concept for a new neutron source and its potential position in the world neutron landscape are discussed. The flagship experiments for a new neutron source in the fields of condensed matter research, fundamental and nuclear physics are proposed. [ru

  18. Russia: Overview of activities on Neutron Imaging (NI) and Cultural Heritage (CH) studies

    International Nuclear Information System (INIS)

    Kozlenko, Denis

    2012-01-01

    The development of neutron imaging techniques as a tool for non-destructive analysis of the internal structure, defects and processes in industrial products, functional materials, objects of cultural heritage attracts considerable attention at the present time. The dedicated instruments are available at the many neutron sources. The IBR-2M high flux pulsed reactor is one of the most powerful pulsed neutron sources in the world with the average power 2 MW, power per neutron pulse 1850 MW and neutron flux in pulse of 5·10 15 n/cm 2 /s. During the period December 2006 – December 2010 the reactor was on modernization for replacement of the reactor vessel and fuel elements. During 2011, the successful physical and power start-up of IBR-2M were performed. Now reactor is operational and can be used for research and development activities using neutron scattering techniques in next 25 years prospective. However, no instruments dedicated for neutron imaging is installed at IBR-2M so far. Moreover, in Russian Federation there is no dedicated neutron imaging facility for cultural heritage research at the moment

  19. Determination of the origin of the medieval glass bracelets discovered in Dubna (Moscow Region, Russia), using the neutron activation analysis

    International Nuclear Information System (INIS)

    Dmitrieva, S.O.; Frontas'eva, M.V.; Dmitriev, A.Yu.; Dmitriev, A.A.

    2016-01-01

    The work is dedicated to the determination of the origin of archaeological finds from medieval glass using the method of neutron activation analysis (NAA). Among such objects we can discover things not only produced in ancient Russian glassmaking workshops but also brought from Byzantium. The authors substantiate the ancient Russian origin of the medieval glass bracelets of pre-Mongol period, found on the ancient Dubna settlement. The conclusions are based on the data about the glass chemical composition obtained as a result of NAA of ten fragments of bracelets at the IBR-2 reactor, FLNP, JINR. [ru

  20. Study of residual stresses in CT test specimens welded by electron beam

    Science.gov (United States)

    Papushkin, I. V.; Kaisheva, D.; Bokuchava, G. D.; Angelov, V.; Petrov, P.

    2018-03-01

    The paper reports result of residual stress distribution studies in CT specimens reconstituted by electron beam welding (EBW). The main aim of the study is evaluation of the applicability of the welding technique for CT specimens’ reconstitution. Thus, the temperature distribution during electron beam welding of a CT specimen was calculated using Green’s functions and the residual stress distribution was determined experimentally using neutron diffraction. Time-of-flight neutron diffraction experiments were performed on a Fourier stress diffractometer at the IBR-2 fast pulsed reactor in FLNP JINR (Dubna, Russia). The neutron diffraction data estimates yielded a maximal stress level of ±180 MPa in the welded joint.

  1. Activation analysis of coal with the help of a microtron

    International Nuclear Information System (INIS)

    Sodnom, N.; Gehrbish, Sh.

    1989-01-01

    Activation analysis techniques using microtron bremsstrahlung and photoneutrons have been developed for the multielemental analysis of coal. Analysis data for coals from 17 mines of Mongolia are presented. The chlorine content of coal and the distribution of elements in coal burning products are determined. Control experiments were performed at the reactors IBR-2 and ARGUS. The results of the gamma activation analysis are compared with neutron activation and X-ray fluorescence analyses data. It is shown that the microtron irradiation techniques employed provide a satisfactory multielemental basis for the analysis of coal. (author)

  2. Independent multi-channel analyzer with the color display and microcomputer in the CAMAC standard

    International Nuclear Information System (INIS)

    Gyunter, Z.; Elizarov, O.I.; Zhukov, G.P.; Mikhaehlis, B.; Shul'tts, K.Kh.

    1983-01-01

    An independent multi-channel time-of-flight analyzer developed for a spectrometer of polarised neutrons and used in experiments with the IBR-2 pulse reactor is described. Different cyclic modes of measuring are realized in the analyzer, 4 kwords of analyzer momory being assigned for each mode. The spectra are displayed on a colour screen during measurements. Simultaneous displaying of up to 8 spectra is possible. A microcomputer transfers the spectra from the buffer analyzer memory to the microcomputer memory. The accumulated information is transferred to the PDP-11/70 central computer

  3. Numerical generalized vibration density of states evaluation for inelastic neutron scattering in solid matter

    CERN Document Server

    Kazmianec, V; Aranghel, D

    2002-01-01

    A computational method for improved evaluation of the generalized vibration density of states (GVDS) is proposed. It is based on Fast Fourier Transform (FPT) technique and gives the possibility for more precise analyses of the neutron double differential scattering cross section. The method was applied to zirconium hydride investigation. The results were presented for ZrH sub 1 sub . sub 6 U sub 0 sub . sub 3 sub 2 sample at various temperatures on time-of-flight (TOF) Spectrometry at IBR-2 reactor of JINR-Dubna and were compared to GVDS values obtained by traditional single-phonon approximation method

  4. System of common usage on the base of external memory devices and the SM-3 computer

    International Nuclear Information System (INIS)

    Baluka, G.; Vasin, A.Yu.; Ermakov, V.A.; Zhukov, G.P.; Zimin, G.N.; Namsraj, Yu.; Ostrovnoj, A.I.; Savvateev, A.S.; Salamatin, I.M.; Yanovskij, G.Ya.

    1980-01-01

    An easily modified system of common usage on the base of external memories and a SM-3 minicomputer replacing some pulse analysers is described. The system has merits of PA and is more advantageous with regard to effectiveness of equipment using, the possibility of changing configuration and functions, the data protection against losses due to user errors and some failures, price of one registration channel, place occupied. The system of common usage is intended for the IBR-2 pulse reactor computing centre. It is designed using the SANPO system means for SM-3 computer [ru

  5. The Dynamic Method for Time-of-Flight Measurement of Thermal Neutron Spectra from Pulsed Sources

    International Nuclear Information System (INIS)

    Pepelyshev, Yu.N.; Tulaev, A.B.; Bobrakov, V.F.

    1994-01-01

    The time-of-flight method for a measurement of thermal neutron spectra in the pulsed neutron sources with high efficiency of neutron registration, more than 10 5 times higher in comparison with traditional one, is described. The main problems connected with the electric current technique for time-of-flight spectra measurement are examined. The methodical errors, problems of a special neutron detector design and other questions are discussed. Some experimental results, spectra from surfaces of the water and solid methane moderators, obtained in the pulsed reactor IBR-2 (Dubna, Russia) are presented. 4 refs., 5 figs

  6. Clustering methods and visualization algorithms to aid nuclear reactor operative diagnostics

    International Nuclear Information System (INIS)

    Pepelyshev, Yu.N.; Dzwinel, W.

    1990-01-01

    The software system developed plays the role of the aid to an operator for nuclear reactor diagnostics. The noise analysis of the reactor parameters such as power, temperature and coolant flow rate constitutes the basis of the system. Combination of data acquisition, data preprocessing, clustering and cluster visualization algorithms with heuristic techniques of results analysis, determine the way of its implementation. Two regimes are available. The first one - extended - is recommended for a long term investigations and the second - suppressed for the aid to the reactor operation monitoring. The system has been tested and developed at the JINR IBR-2 pulsed reactor. 13 refs.; 4 figs.; 2 tabs

  7. Gamma-irradiation and neutron effect on DNA-membrane complexes of mammalian cells

    International Nuclear Information System (INIS)

    Lapidus, I.L.; Nazarov, V.M.; Ehrtsgreber, G.

    1984-01-01

    The first results of radiobiological investigations in the biophysical channel of the JINR reactor IBR-2 are presented. Sedimentation behaviour of DNA-membrane complexes has been studied at irradiation of the Chinese hamster cells (VT9-4) in a wide dose range of 137 Cs γ-irradiation and neutrons. An earlier assumption of the authors on the role of DNA double-strand breaks in changing the relative sedimentation velocity of complexes at irradiation of cells with doses over 50 Gy has been confirmed

  8. Investigation of Fe3O4 Colloid Behaviour in a Magnetic Field by Polarized Neutron Transmission

    International Nuclear Information System (INIS)

    Dokukin, E.B.; Kozhevnikov, S.V.; Nikitenko, Yu.V.; Petrenko, A.V.

    1994-01-01

    Experiments were conducted to measure the dependence of neutron polarization following their transmission through a magnetic colloid on the concentration of magnetic particles, magnetic field strength and wavelength of neutrons. In a magnetic field up to 500 Oe the precession of the neutron polarization is seen. Comparison of the experimental data and theory is made and colloid magnetization is determined. The measurement was carried out with the SPN-1 polarized neutron spectrometer at the high-flux pulsed reactor IBR-2 in Dubna. 7 refs., 2 figs

  9. Determination of the origin of the medieval glass bracelets discovered in Dubna, Moscow Region, Russia, using the neutron activation analysis

    International Nuclear Information System (INIS)

    Dmitrieva, S.O.; Frontasyeva, M.V.; Dmitriev, A.Yu.; Dmitriev, A.A.

    2017-01-01

    The work is dedicated to the determination of the origin of archaeological finds from medieval glass using the method of neutron activation analysis (NAA). Among such objects we can discover things not only produced in ancient Russian glassmaking workshops but also imported from Byzantium. The authors substantiate the ancient Russian origin of the medieval glass bracelets of pre-Mongol period, found on the ancient Dubna settlement. The conclusions are based on data on the glass chemical composition obtained as a result of NAA of 10 fragments of bracelets at the IBR-2 reactor, FLNP, JINR.

  10. Neutron activation of building materials used in the reactor shield

    International Nuclear Information System (INIS)

    Hernandez, A.T.; Perez, G.; D'Alessandro, K.

    1993-01-01

    Cuban concretes and their main components (mineral aggregates and cement) were investigated through long-lived activation products induced by neutrons from a reactor. The multielemental content in the materials studied was obtained by neutron activation analysis in an IBR-2 reactor and gamma activation analysis in an MT-25 microtron from Join Institute of Nuclear Research of Dubna. After irradiation of building materials for 30 years by a neutron flow of unitary density, induced radioactivity was calculated according to experimental data. The comparative evaluation of different concretes aggregates and two types of cement related to the activation properties is discussed

  11. Irradiation tests of ATLAS liquid argon forward calorimeter (FCAL) electronics components

    CERN Document Server

    Leroy, C; Golikov, V; Golubyh, S M; Kukhtin, V; Kulagin, E; Luschikov, V; Merkulov, L; Minashkin, V F; Shalyugin, A N

    2002-01-01

    FCAL resistors, capacitors, and transformers together with capacitors and sintimid disks of the purity monitor have been irradiated in liquid argon to study their possible lead to argon pollution at a maximal neutron fluence of 1016 n cm-2 at the IBR-2 reactor of JINR, Dubna. The results of charge collection measurements before and after irradiation are reported. Electrical measurement on these FCAL capacitors, resistors and transformers were also performed after irradiation. In general, the results of resistance, capacitance, impedance, leakage current and high voltage breakdown measurements after irradiation show minor changes of value only for some parameters from nominal values or values measured before irradiation.

  12. Air Pollution with Heavy Metals and Radionuclides in Slovakia Studied by the Moss Biomonitoring Technique

    CERN Document Server

    Florek, M; Mankovska, B; Oprea, K; Pavlov, S S; Steinnes, E; Sykora, I

    2001-01-01

    Applying the moss biomonitoring technique to air pollution studies in Slovakia, heavy metals, rare-earth elements, actinides (U and Th) were determined in 86 moss samples from the European moss survey 2000 by means of epithermal neutron activation analysis at the IBR-2 reactor (Dubna). Such elements as In, Cu, Cd, Hg and Pb were determined by AAS in the Forest Research Institute, Zvolen (Slovakia). The results of measurement of the natural radionuclides ^{210}Pb, ^{7}Be, ^{137}Cs and ^{40}K in 11 samples of moss are also reported. A comparison with the results from moss surveys 1991 and 1995 revealed previously unknown tendencies of air pollution in the examined areas.

  13. JINR rapid communications

    International Nuclear Information System (INIS)

    1999-01-01

    The present collection of rapid communications from JINR, Dubna, contains seven separate records on additional conditions on eigenvectors in solving inverse problem for two-dimensional Schroedinger equation, on an absolute calibration of deuteron beam polarization at LHE, determination of the vector component of the polarization of the JINR synchrophasotron deuteron beam, wavelet-analysis: criterion of reliable signal selection, on asymptotics in inclusive production of antinuclei and nuclear fragments, use of neutron activation analysis at the IBR-2 reactor for atmospheric monitoring and impulse method for temperature measurement of silicon detectors

  14. Non-destructive diagnostics of irradiated materials using neutron scattering from pulsed neutron sources

    Energy Technology Data Exchange (ETDEWEB)

    Korenev, Sergey E-mail: sergey_korenev@steris.com; Sikolenko, Vadim

    2004-10-01

    The advantage of neutron-scattering studies as compared to the standard X-ray technique is the high penetration of neutrons that allow us to study volume effects. The high resolution of instrumentation on the basis neutron scattering allows measurement of the parameters of lattice structure with high precision. We suggest the use of neutron scattering from pulsed neutron sources for analysis of materials irradiated with pulsed high current electron and ion beams. The results of preliminary tests using this method for Ni foils that have been studied by neutron diffraction at the IBR-2 (Pulsed Fast Reactor at Joint Institute for Nuclear Research) are presented.

  15. Non-destructive diagnostics of irradiated materials using neutron scattering from pulsed neutron sources

    Science.gov (United States)

    Korenev, Sergey; Sikolenko, Vadim

    2004-09-01

    The advantage of neutron-scattering studies as compared to the standard X-ray technique is the high penetration of neutrons that allow us to study volume effects. The high resolution of instrumentation on the basis neutron scattering allows measurement of the parameters of lattice structure with high precision. We suggest the use of neutron scattering from pulsed neutron sources for analysis of materials irradiated with pulsed high current electron and ion beams. The results of preliminary tests using this method for Ni foils that have been studied by neutron diffraction at the IBR-2 (Pulsed Fast Reactor at Joint Institute for Nuclear Research) are presented.

  16. The dynamic method for time-of-flight measurement of thermal neutron spectra from pulsed sources

    International Nuclear Information System (INIS)

    Pepyolyshev, Yu.N.; Chuklyaev, S.V.; Tulaev, A.B.; Bobrakov, V.F.

    1995-01-01

    A time-of-flight method for measurement of thermal neutron spectra in pulsed neutron sources with an efficiency more than 10 5 times higher than the standard method is described. The main problems associated with the electric current technique for time-of-flight spectra measurement are examined. The methodical errors, problems of special neutron detector design and other questions are discussed. Some experimental results for spectra from the surfaces of water and solid methane moderators obtained at the IBR-2 pulsed reactor (Dubna, Russia) are presented. (orig.)

  17. Proposal of a wide-band mirror polarizer of slow neutrons at a pulsed neutron source

    International Nuclear Information System (INIS)

    Nikitenko, Yu.V.; Ostanevich, Yu.M.

    1992-01-01

    The new type wide-band mirror-based neutron polarizer to be operated at a pulsed neutron source is suggested. The idea is to use a movable polarizing mirror system, which, be the incoming beam monochromatized by the time-of-flight, would allow one to tune glancing angles in time so, that the total reflection condition is always fulfilled only for one of the two neutron spin eigenstates. Estimates show, that with the pulsed reactor IBR-2 such polarizer allows one to build a small-angle neutron scattering instrument capable to effectively use the wave-length band from 2 to 15 A. 9 refs.; 1 fig

  18. Neutron scattering for lithium-ion batteries: analysis of materials and processes; Primenenie rasseyaniya nejtronov dlya analiza protsessov v litij-ionnykh akkumulyatorakh

    Energy Technology Data Exchange (ETDEWEB)

    Balagurov, A. M.; Bobrikov, I. A. [Ob' ' edinennyj Inst. Yadernykh Issledovanij, Dubna (Russian Federation); Samojlova, N. Yu. [Ob' ' edinennyj Inst. Yadernykh Issledovanij, Dubna (Russian Federation); Nauchno-Issledovatel' skij Inst. Yadernoj Fiziki im. D.V.Skobel' tsyna, MGU im. V.V.Lomonosova, Moscow (Russian Federation); Drozhzhin, O. A.; Antipov, E. V. [Moskovskij Gosudarstvennyj Univ. im. M.V.Lomonosova, Moscow (Russian Federation)

    2014-07-01

    The use of neutron scattering to study the structure of materials used in portable power sources (mainly lithium-ion batteries) and to examine the structural changes of these materials during the electrochemical processes is reviewed. We consider the applications of several basic techniques: diffraction, small angle and inelastic neutron scattering, neutron reflectometry and neutron imaging. The experimental facilities that already exist in advanced neutron sources and a series of representative experiments are reviewed. The results of some studies of lithium-containing materials and lithium-ion batteries performed at the IBR-2 pulsed research reactor at the Joint Institute for Nuclear Research (Dubna) are presented.

  19. The behavior of a type-II superconductor Nb in a magnetic field as investigated in polarized-neutron transmission experiments

    International Nuclear Information System (INIS)

    Aksenov, V.L.; Dokukin, E.B.; Kozhevnikov, S.V.; Nikitenko, Yu.V.; Petrenko, A.V.

    1995-01-01

    The type-II superconducting polycrystal Nb was investigated on the SPN-1 polarized-neutron spectrometer at the high-intensity pulsed reactor IBR-2 at Dubna. In polarized-neutron transmission experiments the magnetic-field dependence of the neutron beam polarization was measured. Experiments were performed over a wide magnetic-field range from 0 to H c2 at a temperature of 4.8 K. A quasiperiodic variation of the neutron depolarization as a function of magnetic-field strength was observed. (orig.)

  20. Stability of the Hall sensors performance under neutron irradiation

    International Nuclear Information System (INIS)

    Duran, I.; Hron, M.; Stockel, J.; Viererbl, L.; Vsolak, R.; Cerva, V.; Bolshakova, I.; Holyaka, R.; Vayakis, G.

    2004-01-01

    A principally new diagnostic method must be developed for magnetic measurements in steady state regime of operation of fusion reactor. One of the options is the use of transducers based on Hall effect. The use of Hall sensors in ITER is presently limited by their questionable radiation and thermal stability. Issues of reliable operation in ITER like radiation and thermal environment are addressed in the paper. The results of irradiation tests of candidate Hall sensors in LVR-15 and IBR-2 experimental fission reactors are presented. Stable operation (deterioration of sensitivity below one percent) of the specially prepared sensors was demonstrated during irradiation by the total fluence of 3.10 16 n/cm 2 in IBR-2 reactor. Increasing the total neutron fluence up to 3.10 17 n/cm 2 resulted in deterioration of the best sensor's output still below 10% as demonstrated during irradiation in LVR-15 fission reactor. This level of neutron is already higher than the expected ITER life time neutron fluence for a sensor location just outside the ITER vessel. (authors)

  1. New results from air pollution studies in Bulgaria (moss survey 2000-2001)

    International Nuclear Information System (INIS)

    Stamenov, J.; Jovchev, M.; Vachev, B.

    2002-01-01

    New results of moss survey 2000 of systematic study of air pollution with heavy metals and other toxic elements in Bulgaria are reported. The moss samples collected at 103 sites in Bulgaria, along the borders with Yugoslavia, Macedonia, Greece and Turkey were analyzed by instrumental activation analysis using epithermal neutrons (ENAA) at the IBR-2 pulsed fast reactor for a wide set of elements including heavy metals and rare earth elements (Na, Mg, Al, Cl, K, Ca, Sc, V, Cr, Mn, Fe, Co, Ni, Zn, As, Se, Br, Rb, Sr, Mo, Sb, I, Cs, Ba, La, Sm, Tb, Yb, Hf, Ta, W, Au, Th, and U). The results obtained are consistent with the mean European values for most of elements. The principle component analysis is applied to distinguish heavy and light crust elements and vegetation ones from those of anthropogenic origin

  2. An experimental facility for studying delayed neutron emission

    International Nuclear Information System (INIS)

    Dermendzhiev, E.; Nazarov, V.M.; Pavlov, S.S.; Ruskov, Iv.; Zamyatin, Yu.S.

    1993-01-01

    A new experimental facility for studying delayed neutron emission has been designed and tested. A method based on utilization of the Dubna IBR-2 pulsed reactor, has been proposed and realized for periodical irradiation of targets composed of fissionable isotopes. Such a powerful pulsed neutron source in combination with a slow neutron chopper synchronized with the reactor bursts makes possible variation of the exposure duration and effective suppression of the fast neutron background due to delay neutrons emitted from the reactor core. Detection of delayed neutrons from the target is carried out by a high-efficiency multicounter neutron detector with a near-4π geometry. Some test measurements and results are briefly described. Possible use of the facility for other tasks is also discussed. 14 refs.; 14 figs

  3. Proposal of a wide-band mirror polarizer of slow neutrons at a pulsed neutron source

    International Nuclear Information System (INIS)

    Nikitenko, Yu.V.; Ostanevich, Yu.M.

    1993-01-01

    The new type of wide-band mirror-based neutron polarizer, which is to be operated at a pulsed neutron source, is suggested. The idea is to use a movable polarizing mirror system, which, with the incoming beam monochromatized by the time-of-flight, would allow one to tune glancing angles in time so that the total reflection condition is always fulfilled only for one of the two neutron spin eigenstates. Estimates show that with the pulsed reactor IBR-2 such a polarizer allows one to build a small angle neutron scattering instrument capable of effectively using the wavelength band from 2 A with a rather high luminosity (time-averaged flux at sample position being up to 10 7 n/s/cm -2 ). (orig.)

  4. Pulsed neutron sources at Dubna

    International Nuclear Information System (INIS)

    Shabalin, E.P.

    1991-01-01

    In 1960 the first world repetitively pulsed reactor IBR was put into operation. It was the beginning of the story how fission based pulsed neutron sources at Dubna have survived. The engineers involved have experienced many successes and failures in the course of new sources upgrading to finally come to possess the world's brightest neutron source - IBR-2. The details are being reviewed through the paper. The fission based pulsed neutron sources did not reach their final state as yet- the conceptual views of IBR prospects are being discussed with the goal to double the thermal neutron peak flux (up to 2x10 16 ) and to enhance the cold neutron flux by 10 times (with the present one being as high that of the ISIS cold moderator). (author)

  5. A New approach for the data acquisition system of the cairo fourier diffractometer

    International Nuclear Information System (INIS)

    Maayouf, R.M.A.; Khalil, M.I.

    2000-01-01

    The present work deals with a new approach for the reverse time of flight (RTOF) analysis of the diffraction spectra. The approach is based on the same RTOF concept used for the design of a separate RTOF analyzer and applies, for data acquisition, a special interface card and software program installed in a PC computer, to perform the cross-correlation functions between the three signals received from the chopper decoder, detector and the pulsed neutron source respectively. The new approach have been realized for use with a Fourier diffractometer facility based on the RTOF concept. It has been found from test measurements performed with the high resolution Fourier diffractometer (HRFD) at the IBR-2 reactor (JINR, Dubna) that the new approach can successfully replace the RTOF analyzer

  6. Concentration of elements in atmospheric aerosol in Bratislava

    International Nuclear Information System (INIS)

    Meresova, J.; Florek, M.; Holy, K.; Sykora, I.; Frontasyeva, M.V.; Pavlov, S.S.

    2006-01-01

    The concentrations of 41 chemical elements (heavy metals, rare earths, and actinides) were determined in atmospheric aerosol using nuclear and related analytical techniques. The sampling location in Bratislava (Slovak Republic). The main goal of this study is the quantification of the atmospheric pollution and its trend. The elemental content in filters was measured using instrumental neutron activation analysis at IBR-2 reactor in JINR Dubna and by atomic absorption spectrometry in Bratislava. The obtained results confirm the decreasing trend of pollution by most of the heavy metals in Bratislava atmosphere, and they are compared with the contents of pollutants in atmosphere of other cities. We determined also the composition of clear filter materials. (Authors)

  7. Relation between sedimentation behaviour of DNA-membrane complexes and DNA single- and double-strand breaks after irradiation with gamma-rays, pulse neutrons and 12C ions

    International Nuclear Information System (INIS)

    Erzgraber, G.; Lapidus, I.L.

    1985-01-01

    The experimental data on sedimentation behaviour of DNA-membrane complexes at radiation of the Chinese hamster cells (V79-4) in a wide dose range of 127 Cs γ-rays, pulse neutrons (reactor IBR-2, Laboratory of Neutron Physics, JINR, Dubna) are accelerated 12 C ions (cyclotron U-200, Laboratory of Nuclear Reactions, JINR, Dubna) are presented An assumption on the role of DNA single- and double-strend breaks in changing the sedimentation properties of DNA-membrane complexes has been confirmed by the experiments with radiation of different quality. The possibility of estimating induction and repair of DNA breaks on the basis of dependence of the relative sedimentation velocity of complexes on the irradiation does is discussed

  8. Use of the MCL dialog language for autonomous multi-channel analyzer automation

    International Nuclear Information System (INIS)

    Gyunter, Z.; Lebner, M.; Mikhaehlis, B.; Shvenkner, V.; Shul'tts, K.-Kh.

    1985-01-01

    The structure and software of a time-of-flight multichannel analyzer are considered. The analyzer is a subsystem of the measuring module of the SPN-1 polarized neutron spectrometer used in experiments at the IBR-2 reactor. The analyzer operates having several structures differing from one another by a timing coder. The MCL (MULTI-CONTROL-LANGUAGE) system is developed for control of the spectrometer. The system ensures the computer-user conversation and interfacing the computer and the experimental equipment. The MCL language is similar to that of the BASIC or the BAMBI. It has modular structure. The language interpreter and operating system have about 2 kbyte memory. The considered analyser is successfully used already during 6 months. The number of detector inputs of the analyser increased. Expenditures for alternations of programs are negligible due to modular structure of the system. Realization of new commads does not require comprehensive knowledge of the MCL language

  9. Volume concentration of 41 elements in ground level of atmosphere in Bratislava

    International Nuclear Information System (INIS)

    Florek, M.; Meresova, J.; Holy, K.; Sykora, I.; Frontasyeva, M. V.; Pavlov, S. S.

    2006-01-01

    The concentrations of 41 chemical elements (heavy metals, rare earths, and actinides) were determined in atmospheric aerosol using nuclear and related analytical techniques. The sampling location was in Bratislava (Slovak Republic). The main goal of this study is the quantification of the atmospheric pollution and its trend. The elemental content in filters was measured using instrumental neutron activation analysis at IBR-2 reactor in JINR Dubna and by atomic absorption spectrometry in Bratislava. The obtained results confirmed the decreasing trend of pollution by most of the heavy metals in Bratislava atmosphere, and they are compared with the contents of pollutants in atmosphere of other cities. We determined also the composition of clear filter materials. (authors)

  10. URAM-2 Cryogenic Irradiation Facility

    CERN Document Server

    Shabalin, E P; Kulikov, S A; Kulagin, E N; Melihov, V V; Belyakov, A A; Golovanov, L B; Borzunov, Yu T; Konstantinov, V I; Androsov, A V

    2002-01-01

    The URAM-2 irradiation facility has been built and mounted at the channel No. 3 of the IBR-2 reactor. It was constructed for study of radiolysis effects by fast neutron irradiation in some suitable for effective cold neutron production materials (namely: solid methane, methane hydrate, water ice, etc.). The facility cooling system is based on using liquid helium as a coolant material. The original charging block of the rig allows the samples to be loaded by condensing gas into irradiation cavity or by charging beads of ice prepared before. Preliminary tests for each facility block and assembling them at the working position were carried out. Use of the facility for study accumulation of chemical energy under irradiation at low temperature in materials mentioned above and its spontaneous release was started.

  11. Excitation of long living isomers 107m,109m Ag in the fast neutron inelastic scattering reactions

    International Nuclear Information System (INIS)

    Alpatov, V.G.; Borzakov, S.B.; Chinaeva, V.P

    1999-01-01

    The cross sections for excitation of 107m,109m Ag isomeric states are measured in the reactions of inelastic scattering of reactor fast neutrons. The measurements were performed on the rabbit tube 'Regata' of the IBR-2 reactor (JINR, Dubna). The method consisted in comparing the γ-line intensities of silver isomers with the 103m Rh isomer irradiated in the same neutron flux. The cross sections of 103 Rh are well known in wide range of neutron energy. The measured values are the following: σ( 107m Ag) = 204 ± 18 mb, σ( 109m Ag) = 262 ± 26 mb. The estimate is made of the possible yield of 109m Ag isomeric nuclei if one uses the high-current proton accelerator with heavy target to produce fast neutrons in reactions of spallation. (authors)

  12. Atmospheric deposition of trace elements around Ulan Bator city studied by moss and lichen biomonitoring technique and INAA

    International Nuclear Information System (INIS)

    Ganbold, G.; Gehrbish, Sh.; Tsehndehehkhuu, Ts.; Gundorina, S.F.; Frontas'eva, M.V.; Ostrovnaya, T.M.; Pavlov, S.S.

    2005-01-01

    For the first time the moss and lichen biomonitoring technique has been applied to air pollution in Mongolia (Ulan-Bator, the capital city). INAA at the IBR-2 reactor has made it possible to determine the content of 35 elements in moss and lichen biomonitors. Samples collected at sites located 10-15 km from the center of Ulan-Bator were analyzed by Instrumental Neutron Activation Analysis (INAA) using epithermal neutrons. The mosses (Rhytidium rugosum, Thuidium abietinum, Entodon concinnus) and lichens (Cladonia stellaris, Parmelia separata) were used to study the atmospheric deposition of trace elements. It was shown that the suggested types of mosses could be used as suitable biomonitors to estimate the concentration levels of heavy metals and trace elements in Ulan-Bator atmospheric deposition. The results are compared to the data of atmospheric deposition of some European countries

  13. Thermal diffuse scattering in time-of-flight neutron diffraction studied on SBN single crystals

    International Nuclear Information System (INIS)

    Prokert, F.; Savenko, B.N.; Balagurov, A.M.

    1994-01-01

    At time-of-flight (TOF) diffractometer D N-2, installed at the pulsed reactor IBR-2 in Dubna, Sr x Ba 1-x Nb 2 O 6 mixed single crystals (SBN-x) of different compositions (0.50 < x< 0.75) were investigated between 15 and 773 K. The diffraction patterns were found to be strongly influenced by the thermal diffuse scattering (TDS). The appearance of the TDS from the long wavelength acoustic models of vibration in single crystals is characterized by the ratio of the velocity of sound to the velocity of neutron. Due to the nature of the TOF Laue diffraction technique used on D N-2, the TDS around Bragg peaks has rather a complex profile. An understanding of the TDS close to Bragg peaks is essential in allowing the extraction of the diffuse scattering occurring at the diffuse ferroelectric phase transition in SBN crystals. 11 refs.; 9 figs.; 1 tab. (author)

  14. Neutron scattering investigations of the lipid bilayer structure pressure dependence

    Directory of Open Access Journals (Sweden)

    D. V. Soloviov

    2012-03-01

    Full Text Available Lipid bilayer structure investigation results obtained with small angle neutron scattering method at the Joint Institute for Nuclear Research IBR-2M nuclear reactor (Dubna, Russia are presented. Experiment has been per-formed with small angle neutron scattering spectrometer YuMO, upgraded with the apparatus for performing P-V-T measurements on the substance under investigation. D2O-1,2-dipalmitoyl-sn-glycero-3-phosphocholine (DPPC liquid system, presenting the model of natural live membrane, has been taken as the sample for investiga-tions. The lipid bilayer spatial period was measured in experiment along with isothermal compressibility simulta-neously at different pressures. It has been shown, that the bilayer structural transition from ripple (wavelike gel-phase phase to liquid-crystal phase is accompanied with anomalous rise of isothermal compressibility, indicat-ing occurrence of the phase transition.

  15. Atmospheric Deposition of Trace Elements Around Ulan-Bator City Studied by Moss and Lichen Biomonitoring Technique and INAA

    CERN Document Server

    Ganbold, G; Gundorina, S F; Frontasyeva, M V; Ostrovnaya, T M; Pavlov, S S; Tsendeekhuu, T

    2005-01-01

    For the first time the moss and lichen biomonitoring technique has been applied to air pollution in Mongolia (Ulan-Bator, the capital city). INAA at the IBR-2 reactor has made it possible to determine the content of 35 elements in moss and lichen biomonitors. Samples collected at sites located 10-15 km from the center of Ulan-Bator were analyzed by Instrumental Neutron Activation Analysis (INAA) using epithermal neutrons. The mosses (\\textit{Rhytidium rugosum}, \\textit{Thuidium abietinum}, \\textit{Entodon concinnus}) and lichens (\\textit{Cladonia stellaris}, \\textit{Parmelia separata}) were used to study the atmospheric deposition of trace elements. It was shown that the suggested types of mosses could be used as suitable biomonitors to estimate the concentration levels of heavy metals and trace elements in Ulan-Bator atmospheric deposition. The results are compared to the data of atmospheric deposition of some European countries.

  16. New Results from Air Pollution Studies in Bulgaria (Moss Survey 2000-2001)

    CERN Document Server

    Stamenov, J N; Vachev, B; Gueleva, E; Yurukova, L; Ganeva, A; Mitrikov, M; Antonov, A; Srentz, A; Varbanov, Z; Batov, I V; Damov, K; Marinova, E; Frontasyeva, M V; Pavlov, S S; Strelkova, L P

    2002-01-01

    New results of moss survey 2000 of systematic study of air pollution with heavy metals and other toxic elements in Bulgaria are reported. The moss samples collected at 103 sites in Bulgaria, along the borders with Yugoslavia, Macedonia, Greece and Turkey were analyzed by instrumental activation analysis using epithermal neutrons (ENAA) at the IBR-2 pulsed fast reactor for a wide set of elements including heavy metals and rare earth elements (Na, Mg, Al, Cl, K, Ca, Sc, V, Cr, Mn, Fe, Co, Ni, Zn, As, Se, Br, Rb, Sr, Mo, Sb, I, Cs, Ba, La, Sm, Tb, Yb, Hf, Ta, W, Au, Th, and U). The results obtained are consistent with the mean European values for most of elements. The principle component analysis is applied to distinguish heavy and light crust elements and vegetation ones from those of anthropogenic origin.

  17. The dynamics of ammonium ions in K1-x(NH4)xCl mixed crystals by the neutron scattering study

    International Nuclear Information System (INIS)

    Smirnov, L.S.; Natkanets, I.; Shuvalov, L.A.; Dolbinina, V.V.

    2004-01-01

    The study of vibrational spectrum of the K 1-x (NH 4 ) x Cl mixed crystals in a dynamically disordered cubic α-phase at 10 K is carried out by means of inelastic incoherent neutron scattering on the NERA-PR time-of-flight spectrometer set at the IBR-2 reactor (JINR, Dubna). It is shown that low-energy modes of ammonium ions with the energies 19-23 and 62-63 cm -1 at 10 K are observed only within the disordered cubic α-phase and are absent in the ordered cubic δ-phase of NH 4 Cl. The energies of local translation and libration modes of ammonium ions are determined in the α- and δ-phases of the K 1-x (NH 4 ) x Cl mixed crystals

  18. X – ray and neutron diffraction of TiAl alloys

    International Nuclear Information System (INIS)

    Valkov, Stefan; Petrov, Peter; Neov, Dimitar; Beskrovny, Anatoly; Kozlenko, Denis

    2015-01-01

    TiAl alloys were prepared by electron beam hybrid method. Composite Ti-Al film, from composite target, was deposited on Ti substrate by electron beam evaporation, followed by electron beam treatment with scanning electron beam. Experiments were made using Leybold Heraus (EWS 300/ 15 - 60) with the following technological parameters : accelerating voltage U = 60kV; beam current I=40 mA, speed of movement of specimens V=5 cm/s, current of the focusing lens If =512mA, specimen distance D0 = 38cm. X- ray and neutron diffraction methods were used to determine the phase composition on the surface and at the volume, respectively. Time of flight neutron diffraction study of TiAl specimens was performed on DN-2 diffractometer at fast pulsed IBR-2 reactor in FLNP JINR (Dubna, Russia).We found that intermetallic TiAl phases were successfully obtained on the surface, as well as in the volume.

  19. Description of the structural evolution of a hydrating portland cement paste by SANS

    International Nuclear Information System (INIS)

    Haeussler, F.; Eichhorn, F.; Baumbach, H.

    1994-01-01

    On the spectrometer MURN at the pulsed reactor IBR-2 dry Portland cement, silica fume, and a hydrating Portland cement paste were studied by small-angle neutron scattering (SANS). By using the TOF-method a momentum transfer from 0.07 nm -1 to 7 nm -1 is detectable. Every component (dry cement powder, clinker minerals, hydrating cement pastes) shows a different scattering behaviour. In the measured Q-region the hardening cement paste does not show a Porod-like behaviour of SANS-curves. In contrast the Porod's potential law holds for dry powder samples of clinker minerals and silica fume. In experiments carried out to observe the hydration progress within the first 321 days the characteristics of the scattering curves (potential behaviour, the radius of gyration, and the macroscopic scattering cross section at Q = 0 nm -1 were measured. Some evolution of the inner structure of the hardened cement paste was noted. (orig.)

  20. Pattern recognition, neural networks, genetic algorithms and high performance computing in nuclear reactor diagnostics. Results and perspectives

    International Nuclear Information System (INIS)

    Dzwinel, W.; Pepyolyshev, N.

    1996-01-01

    The main goal of this paper is the presentation of our experience in development of the diagnostic system for the IBR-2 (Russia - Dubna) nuclear reactor. The authors show the principal results of the system modifications to make it work more reliable and much faster. The former needs the adaptation of new techniques of data processing, the latter, implementation of the newest computational facilities. The results of application of the clustering techniques and a method of visualization of the multi-dimensional information directly on the operator display are presented. The experiences with neural nets, used for prediction of the reactor operation, are discussed. The genetic algorithms were also tested, to reduce the quantity of data nd extracting the most informative components of the analyzed spectra. (authors)

  1. Neutron Diffraction Study of the High-Tc Superconductor HgBa2CaCu2O6.3 under High Pressure

    International Nuclear Information System (INIS)

    Aksenov, V.L.; Balagurov, A.M.; Savenko, B.N.; Capponi, J.J.; Glazkov, V.P.; Goncharenko, I.N.; Somenkov, V.A.

    1994-01-01

    The pressure dependence of the crystal structure of a powder sample of HgBa 2 CaCu 2 O 6.3 (T c =123 K) was studied in the pressure range of 0 to 3.6 GPa, using the DN-12 time-of-flight diffractometer at the IBR-2 pulsed reactor and a sapphire anvil cell chamber. At P=0 the results are in a good accordance with the published data. At P=3.0 and 3.6 GPa the best fit of the experimental data was achieved using the structural model with apical oxygen disordered in the (a,b) plane. The compressibility values of the lattice constants and selected bonds were calculated from the structural data. The highest absolute value of compressibility was found for the distance between the O atom layers. 12 refs., 6 figs., 3 tabs

  2. Neutron scattering investigations of the lipid bilayer structure pressure dependence

    International Nuclear Information System (INIS)

    Solovjov, D.V.; Gordelyij, V.Yi.; Gorshkova, Yu.Je.; Yivan'kov, O.Yi.; Koval'ov, Yu.S.; Kuklyin, A.Yi.; Solovjov, D.V.; Bulavyin, L.A.; Yivan'kov, O.Yi.; Nyikolajenko, T.Yu.; Kuklyin, A.Yi.; Gordelyij, V.Yi.; Gordelyij, V.Yi.

    2012-01-01

    Lipid bilayer structure investigation results obtained with small angle neutron scattering method at the Joint Institute for Nuclear Research IBR-2M nuclear reactor (Dubna, Russia) are presented. Experiment has been performed with small angle neutron scattering spectrometer YuMO, upgraded with the apparatus for performing PV-T measurements on the substance under investigation. D 2 O-1,2-dipalmitoyl-sn-glycero-3-phosphocholine (DPPC) liquid system, presenting the model of natural live membrane, has been taken as the sample for investigations. The lipid bilayer spatial period was measured in experiment along with isothermal compressibility simultaneously at different pressures. It has been shown, that the bilayer structural transition from ripple (wavelike gel-phase) phase to liquid-crystal phase is accompanied with anomalous rise of isothermal compressibility, indicating occurrence of the phase transition.

  3. The Small-Angle Neutron Scattering Data Analysis of the Phospholipid Transport Nanosystem Structure

    Science.gov (United States)

    Zemlyanaya, E. V.; Kiselev, M. A.; Zhabitskaya, E. I.; Aksenov, V. L.; Ipatova, O. M.; Ivankov, O. I.

    2018-05-01

    The small-angle neutron scattering technique (SANS) is employed for investigation of structure of the phospholipid transport nanosystem (PTNS) elaborated in the V.N.Orekhovich Institute of Biomedical Chemistry (Moscow, Russia). The SANS spectra have been measured at the YuMO small-angle spectrometer of IBR-2 reactor (Joint Institute of Nuclear Research, Dubna, Russia). Basic characteristics of polydispersed population of PTNS unilamellar vesicles (average radius of vesicles, polydispersity, thickness of membrane, etc.) have been determined in three cases of the PTNS concentrations in D2O: 5%, 10%, and 25%. Numerical analysis is based on the separated form factors method (SFF). The results are discussed in comparison with the results of analysis of the small-angle X-ray scattering spectra collected at the Kurchatov Synchrotron Radiation Source of the National Research Center “Kurchatov Institute” (Moscow, Russia).

  4. Detector for the FSD Fourier-diffractometer based on ZnS(Ag)/6LiF scintillation screen and wavelength shifting fibers readout

    International Nuclear Information System (INIS)

    Kuz'min, E.S.; Balagurov, A.M.; Bokuchava, G.D.; Zhuk, V.V.; Kudryashev, V.A.; Bulkin, A.P.; Trunov, V.A.

    2001-01-01

    At the IBR-2 pulsed reactor (FLNP, JINR, Dubna), a specialized time-of-flight instrument Fourier-Stress-Diffractometer (FSD) intended for the measurement of internal stresses in bulk samples by using high-resolution neutron diffraction is under construction. One of the main components of the diffractometer is a new-type detector with combined electronic - geometrical focusing uniting a large solid angle and a small geometry contribution to the instrumental resolution. The first two modules of the detector, based on scintillation screen ZnS(Ag)/ 6 LiF with wavelength shifting fibers readout have been developed and tested. The design of the detector and associated electronics are described. The method of time focusing surface approximation, using the screen flexibility is proposed. Characteristics of the tested modules in comparison with a detector of the previous generation are presented and advantages of the new detector design for high-resolution diffractometry are discussed

  5. Research and Development for the ATLAS Forward Calorimetry at the HL-LHC

    CERN Document Server

    Cheplakov, Alexander

    2015-01-01

    A total luminosity of 3000/fb is expected at the HL-LHC, which corresponds to total irradiation doses which are more than doubled compared to the original design, taking into account a safety factor of 2 representing our confidence in radiation background simulations. Moreover, the increased instantaneous luminosity will result in a much higher detector occupancy. The ATLAS Forward Calorimeters (FCal) will be affected by these factors. A rich R&D program is ongoing to evaluate the consequences of the LHC modernization and to investigate di_erent scenarios proposed for the Phase-II detector upgrade. This contribution will concentrate on simulation studies of the FCal degradation and on irradiation tests performed at the IBR-2m reactor in Dubna. Results from radiation-tolerant sensors and components of the future read-out and voltage distribution system for various upgrade options of the forward calorimetry will be presented.

  6. An accurate redetermination of the 118Sn binding energy

    International Nuclear Information System (INIS)

    Borzakov, S.B.; Panteleev, Ts.Ts.; Telezhnikov, S.A.; Chrien, R.E.; Faikow-Stanczyk, H.; Grigor'ev, Yu.V.; Pospisil, S.; Smotritskij, L.M.

    2001-01-01

    The energy of well-known strong γ-line from 198 Au, the 'gold standard', has been modified in the light of new adjustments in the fundamental constants and the value of 411.80176(12) keV was determined which is 0.29 eV lower than the latest 1999 value. An energy calibration procedure for determining the neutron binding energy, B n , from complicated (n,γ)-spectra has been developed. A mathematically simple minimization function consisting only of terms having as parameters the coefficients of the energy calibration curve (polynomial) is used. A priori information about the relationships among the energies of different peaks on the spectrum was taken into account by a Monte Carlo simulation. The procedure was used in obtaining of B n for 118 Sn and 64 Cu. The γ-ray spectrum from thermal neutron radiative capture by 117 Sn has been measured on the IBR-2 pulsed reactor. γ-rays were detected by a 72 cm 2 HPGe-detector. B n for 64 Cu was obtained from two γ-spectra. One spectrum was measured on the IBR-2 by the same detector. The other spectrum was measured with a pair spectrometer at the Brookhaven High Flux Beam Reactor. From these two spectra B n for 64 Cu was determined equal to 7915.52(8) keV. The mean value of two most precise results of B n for 118 Sn was determined to be 9326.35(9) keV. The B n for 57Fe was determined to be 7646.08(9) keV

  7. Mechanistic aspects of the reaction between Br2 and chalcogenone donors (LE; E=S, Se): competitive formation of 10-E-3, T-shaped 1:1 molecular adducts, charge-transfer adducts, and [ (LE)2]2+ dications.

    Science.gov (United States)

    Aragoni, M C; Arca, M; Demartin, F; Devillanova, F A; Garau, A; Isaia, F; Lelj, F; Lippolis, V; Verani, G

    2001-07-16

    parallel planes; this gives rise to a graphite-like stacking. The new crystalline modification of 10, obtained from acetonitrile solution, confirms the importance of short intermolecular contacts in determining the asymmetry of Br-E-Br (E = S, Se) and I-Se-I groups in hypervalent 10-E-3 compounds. The analogies in the conductometric and spectrophotometric titrations of 1 and 2-4 with Br2, together with the similarity of the vibrational spectra of 11-14, also imply a T-shaped nature for 11. The vibrational properties of the Br-E-Br (E = S, Se) systems resemble those of the Br3- and IBr2- anions: the Raman spectrum of a symmetric Br-E-Br group shows only one peak near 160 cm(-1), as found for symmetric Br3- and IBr2- anions, while asymmetric Br-E-Br groups also show an antisymmetric Br-E-Br mode at around 190 cm(-1), as observed for asymmetric Br3- and IBr2- ions. Therefore, simple IR and Raman measurements provide a useful tool for distinguishing between symmetric and asymmetric Br-E-Br groups, and hence allow predictions about the crystal packing of these hypervalent chalcogen compounds to be made when crystals of good quality are not available.

  8. Epithermal neutron activation analysis for studying the environment

    International Nuclear Information System (INIS)

    Frontas'eva, M.V.; Steinnes, E.

    1997-01-01

    Epithermal neutron activation analysis (ENAA) has certain advantages over the conventional instrumental analysis (INAA) in terms of improvement in precision and lowering of detection limits, reduction of high matrix activity and fission interferences if any. The current status and the applications of ENAA to environmental samples are reviewed. Experience in the use of ENAA in the monitoring of atmospheric depositions by means of moss-biomonitors at pulsed fast reactor IBR-2 in Dubna is summarized. INAA has shown to be useful for a number of sample types of interest in environmental studies, and should find more extensive use in this area. Analysis of airborne particulate matter is a case where ENAA should be particularly useful. A similar case where ENAA has shown strong performance is in the analysis of mosses used as biomonitors of atmospheric deposition, where 45 elements were determined. In this and other cases, however, induction-coupled plasma mass spectrometry is a very strong competitor, offering data for even more elements. A comparison of ENAA and ICP-MS for moss analysis is presented, and cases where ENAA is unique are discussed

  9. Peculiarities of neutron interaction with boron containing semiconductors

    International Nuclear Information System (INIS)

    Didyk, A.Yu.; ); Hofman, A.; Institute of Atomic Energy, Otwock/Swierk; Vlasukova, L.A.

    2009-01-01

    The results of point defect creation calculation in B 4 C, BN and BP semiconductor single crystals irradiated in the fast neutron reactor IBR-2 are presented. It has been shown that during the thermal neutron interaction with light isotope boron atoms ( 10 B) the damage creation by means of fission nuclear reaction fragments (alpha particles and 7 Li recoil nuclei) exceeds the damage created by fast neutrons (E n > 0.1 MeV) by more than two orders of value. It has been concluded that such irradiation can create a well developed radiation defect structure in boron-containing crystals with nearly homogeneous vacancy depth distribution. This may be used in technological applications for more effective diffusion of impurities implanted at low energies or deposited onto the semiconductor surface. The developed homogeneous vacancy structure is very suitable for the radiation enhanced diffusion of electrically charged or neutral impurities from the surface into the technological depth of semiconductor devices under post irradiation treatment. (authors)

  10. Air Pollution Studies in Central Russia (Tula Region) Using Moss Biomonitoring Technique, NAA and AAS

    CERN Document Server

    Ermakova, E V; Steinnes, E

    2002-01-01

    For the first time the moss biomonitoring technique has been applied to air pollution monitoring in Central Russia (Tula Region). Moss samples were collected from 83 sites in accordance with the sampling strategy of European projects on biomonitoring of atmospheric deposition. Neutron activation analysis (NAA) at the IBR-2 reactor has made it possible to determine the concentration of 33 elements (Na, Mg, Al, Cl, K, Ca, Sc, V, Cr, Mn, Fe, Co, Ni, Zn, As, Br, Rb, Sr, Mo, Sb, I, Cs, Ba, La, Ce, Sm, Tb, Yb, Hf, Ta, W, Th, U) over a large concentration range (from 10000 mg/kg for K to 0.001 mg/kg for Tb and Ta). In addition to NAA, flame AAS (atomic absorption spectrometry) was applied to determine the concentration of Cd, Cu and Pb. Factor analysis was applied to determine possible sources of elements detected in the investigated mosses. Eight factors were identified. The geographical distribution of factor scores is presented. The interpretation of the factor analysis findings points to natural as well as anthr...

  11. Atmospheric depositions of rare earth elements in Albania studied by the moss biomonitoring technique, neutron activation analysis and GIS technology

    International Nuclear Information System (INIS)

    Allajbeu, Sh.; Lazo, P.; Yushin, N.S.; Frontasyeva, M.V.; Qarri, F.; Duliu, O.G.

    2015-01-01

    Rare earth elements (REE) are conservative elements, scarcely derived from anthropogenic sources. The mobilization of REE in the environment requires their monitoring in environmental matrices, where they are mainly present at trace levels. The results on determination of the content of 11 elements by epithermal neutron activation analysis (ENAA) at the IBR-2 reactor in Dubna in carpet-forming moss species Hypnum cupressiforme collected from 44 sampling sites over the whole Albanian territory are presented and discussed. The paper is focused on Sc and lanthanides, as well as Fe and Th, the last ones showing correlations with the investigated REE. With the exception of Fe, all other elements were never determined in the air deposition of Albania. The STATISTICA"T"M 10 software was used for data analysis. The median values for the content of elements under investigation were compared to those in Bulgaria, Macedonia, Romania and Serbia, as well as Norway selected as a pristine area. Therefore, it was shown that the accumulation of REE in mosses is associated with the wind blown metal-enriched soils that are pointed out as the main emitting factor. [ru

  12. Ways of providing radiation resistance of magnetic field semiconductor sensors

    CERN Document Server

    Bolshakova, I A; Holyaka, R; Matkovskii, A; Moroz, A

    2001-01-01

    Hall magnetic field sensors resistant to hard ionizing irradiation are being developed for operation under the radiation conditions of space and in charged particle accelerators. Radiation resistance of the sensors is first determined by the properties of semiconductor materials of sensitive elements; we have used microcrystals and thin layers of III-V semiconductors. Applying complex doping by rare-earth elements and isovalent impurities in certain proportions, we have obtained magnetic field sensors resistant to irradiation by fast neutrons and gamma-quanta. Tests of their radiation resistance were carried out at IBR-2 at the Joint Institute for Nuclear Research (Dubna). When exposed to neutrons with E=0.1-13 MeV and intensity of 10 sup 1 sup 0 n cm sup - sup 2 s sup - sup 1 , the main parameter of the sensors - their sensitivity to magnetic fields - changes by no more than 0.1% up to fluences of 10 sup 1 sup 4 n cm sup - sup 2. Further improvement of radiation resistance of sensor materials is expected by ...

  13. Radioanalytical investigations at FLNP JINR: State of the art

    International Nuclear Information System (INIS)

    Frontasyeva, M.

    2006-01-01

    In spite of competing non-nuclear analytical techniques (AAS, ICP-ES, ICP-MS, etc), reactor neutron activation analysis (NAA) continues to be the most powerful multi-element analytical technique used in geosciences, life sciences and material sciences. NAA, being a technique based on a physical principle different from those of other trace element techniques, should always be used, if feasible, when the need for better quantification of trace elements at ultra-low levels is desirable. In the certification of reference material, NAA as an accurate technique has played and is still playing a key role, even for elements where other techniques have replaced NAA in practical work. The radioanalytical complex REGATA at the IBR-2 reactor for more than 20 years of operation has become a source of analytical data for a considerable number of international projects carried out by specialists from the JINR member- and non-member states. Experience in applying conventional and epithermal neutron activation analysis for some challenging areas of studying the environment is reviewed. Special emphasis is made on collaborative projects with Turkish scientists

  14. Experimental study of swelling of irradiated solid methane during annealing

    International Nuclear Information System (INIS)

    Shabalin, E.; Fedorov, A.; Kulagin, E.; Kulikov, S.; Melikhov, V.; Shabalin, D.

    2008-01-01

    Solid methane, notwithstanding its poor radiation properties, is still widely in use at pulsed neutron sources. One of the specific problems is radiolytic hydrogen gas pressure on the walls of a methane chamber during annealing of methane. Results of experimental study of this phenomenon under fast neutron irradiation with the help of a specially made low temperature irradiation rig at the IBR-2 pulsed reactor are presented. Peak pressure on the wall of the experimental capsule during heating of a sample irradiated at 23-35 K appeared to have a maximum of 27 bar at the absorbed dose 20 MGy, and then falls down with higher doses. Pressure always reached its peak value within the temperature range 72-79 K. Generally, three phases of methane swelling during heating can be distinguished, each characterized by proper rate and intensity. Results of this study were accounted for in design of the solid methane moderator of the second target station of the ISIS facility (England)

  15. Preparation of FMD type A87/IRN inactivated vaccine by gamma irradiation and the immune response on guinea pig

    International Nuclear Information System (INIS)

    Sedeh, Farahnaz Motamedi; Shafaee, Kamal; Fatolahi, Hadi; Arbabi, Kourosh; Khorasani, Akbar

    2008-01-01

    FMD is one of the most economically damaging diseases that affect livestock animals. In this study FMD Virus type A87/IRN was multiplied on BHK21 cells. The virus was titrated by TCID50 method, it was 10 7.5 /ml. The FMD virus samples were inactivated by gamma ray from 60 Co source at -20 deg C. Safety test was done by IBRS2 monolayer cell culture method, also antigenicity of irradiated and un-irradiated virus samples were studied by Complement Fixation Test. The dose/survival curve for irradiated FMD Virus was drawn, the optimum dose range for inactivation of FMDV type A87/IRN and unaltered antigenicity was obtained 40-44 kGy. The inactivated virus samples by irradiation and ethyleneimine (EI) were formulated respectively as vaccine with Al(OH) 3 gel and other substances. The vaccines were inoculated to Guinea pigs and the results of Serum Neutralization Test for the normal vaccine and radio-vaccine showed protective titer after 8 months. The potency test of the inactivated vaccines was done, PD50 Value of the vaccines were calculated 7.06 and 5.6 for inactivated vaccine by EI and gamma irradiation respectively. (author)

  16. An Accurate Redetermination of the $^{118}Sn$ Binding Energy

    CERN Document Server

    Borzakov, S B; Faikow-Stanczyk, H; Grigoriev, Yu V; Panteleev, T; Pospísil, S; Smotritsky, L M; Telezhnikov, S A

    2001-01-01

    The energy of well-known strong {gamma}-line from {{^198}Au}, the "gold standard", has been modified in the light of new adjustments in the fundamental constants and the value of 411.80176(12) keV was determined which is 0.29 eV lower than the latest 1999 value. An energy calibration procedure for determining the neutron binding energy, {B_n}, from complicated {(n , gamma)}-spectra has been developed. A mathematically simple minimization function consisting only of terms having as parameters the coefficients of the energy calibration curve (polynomial) is used. A priori information about the relationships among the energies of different peaks on the spectrum is taking into account by a Monte Carlo simulation. The procedure was used in obtaining of {B_n} for {{^118}Sn} and {{^64}Cu}. The {gamma}-ray spectrum from thermal neutron radiative capture by {{^117}Sn} has been measured on the IBR-2 pulsed reactor. {gamma}-rays were detected by a 72 cm^3 HPGe-detector. {B_n} for {{^64}Cu} was obtained from two {gamma}-...

  17. An accurate redetermination of the sup 1 sup 1 sup 8 Sn binding energy

    CERN Document Server

    Borzakov, S B; Faikow-Stanczyk, H; Grigoriev, Y V; Panteleev, T; Pospísil, S; Smotritsky, L M; Telezhnikov, S A

    2002-01-01

    The energy of well-known strong gamma line from sup 1 sup 9 sup 8 Au, the 'gold standard', has been modified in the light of new adjustments in the fundamental constants and the value of 411.80176(12) keV was determined, which is 0.29 eV lower than the latest 1999 value. An energy calibration procedure for determining the neutron binding energy, B sub n , from complicated (n, gamma) spectra has been developed. A mathematically simple minimization function consisting only of terms having as parameters the coefficients of the energy calibration curve (polynomial) is used. A priori information about the relationships among the energies of different peaks on the spectrum is taken into account by a Monte-Carlo simulation. The procedure was used in obtaining B sub n for sup 1 sup 1 sup 8 Sn. The gamma-ray spectrum from thermal neutron radiative capture by sup 1 sup 1 sup 7 Sn has been measured on the IBR-2 pulsed reactor. gamma-rays were detected by a 72 cm sup 3 HPGe detector. For a better determination of B sub n...

  18. Novel tendencies in developing small-angle neutron scattering methods for studying the structure of biological macromolecules

    International Nuclear Information System (INIS)

    Serdyuk, I.

    1995-01-01

    In recent 20 years thermal neutron scattering has been acknowledged an important instrument for structural studies in molecular biology. The methods of neutron diffraction of high resolution, which are not discussed in this paper, have already permitted to obtain a detailed representation of the course of proteolytic reactions and have arisen a number of new problems connected with the localization of water molecules and the H-D exchange. The methods of low resolution widely used due to a relative simplicity of the experiment have been successfully applied for both solving structural problems per se and investigating the changes in the structure when macromolecules perform their biological functions. The most promising are novel experimental approaches: the triple isotopic substitution method and the method of spin dynamic polarization. These methods ensure solving structural problems at a higher resolution than the dimensions of the macromolecules studied. Installation of new experimental instruments makes neutron measurements more accessible, and development of direct methods for interpretation of experimental data using the apparatus of spherical harmonics opens new possibilities for small-angle neutron scattering making it a necessary element for interpretation of diffraction data of monocrystals of intricate biological macromolecules. The paper presents a brief account of the tendencies in theoretical development and practical use of small-angle scattering for studying biological macromolecules. Special attention is given to the studies carried out in the Laboratory of Neutron Physics on a unique pulse IBR-2 reactor. (author) 14 refs

  19. Heavy Metals and Trace Elements Atmospheric Deposition Studies in Tula Region Using Moss Biomonitors Technique

    CERN Document Server

    Ermakova, E V; Steinnes, E

    2002-01-01

    For the first time the moss biomonitors technique was used in air pollution studies in Tula Region (Central Russia), applying NAA, AAS. Moss samples were collected at 83 sites in accordance with the sampling strategy adopted in European projects on biomonitoring atmospheric deposition. A wide set of trace elements in mosses was determined. The method of epithermal neutron activation at IBR-2 reactor of FLNP JINR has made it possible to identify 33 elements (Na, Mg, Al, Cl, K, Ca, Sc, V, Cr, Mn, Fe, Co, Ni, Zn, As, Br, Rb, Sr, Mo, Sb, I, Cs, Ba, La, Ce, Sm, Tb, Yb, Hf, Ta, W, Th, U) in the large-scale concentration range - from 10000 ppm for K to 0,001 ppm for Tb and Ta. Cu, Cd and Pb were determined by the flame AAS in the Norwegian Institute of Science and Technology. Using the graphical technique and principal component analysis allowed to separate plant, crustal and general pollution components in the moss. The obtained data will be used for constructing coloured maps of the distribution of elements over t...

  20. New Results from Air Pollution Studies in Romania

    CERN Document Server

    Stan, O A; Frontasyeva, M V; Steinnes, E

    2000-01-01

    Results from the next stage of the project "Atmospheric Deposition of Heavy Metals in Rural and Urban Areas of Romania Studied by the Moss Biomonitoring Technique Employing Nuclear and Related Analytical Techniques", carried out under the auspieces of the International Atomic Energy Agency, Vienna, are reported. A total of 70 moss samples (Hypnum Cupressiforme) were collected from highly polluted areas in the north-eastern part of Transylvania during the summer of 1999. The samples were analyzed by epithermal neutron activation analysis at the pulsed fast reactor IBR-2 at JINR, Dubna, for a wide range of elements including heavy metals and rare earths (Na, Mg, Al, Cl, K, Ca, Sc, V, Cr, Mn, Fe, Co, Ni ((n,p) reaction), Cu, Zn, As, Se, Br, Rb, Sr, Zr, Mo, Ag, Sn, Sb, I, Cs, Ba, La, Ce, Nb, Sm, Eu, Gd, Tb, Hf, Ta, W, Au, Th, and U). IAEA certified reference materials were used to ensure the quality of the measurements. The regional extent of pollution patterns of specific metals was determined. Like another stro...

  1. Subcellular distribution of swine vesicular disease virus proteins and alterations induced in infected cells: A comparative study with foot-and-mouth disease virus and vesicular stomatitis virus

    International Nuclear Information System (INIS)

    Martin-Acebes, Miguel A.; Gonzalez-Magaldi, Monica; Rosas, Maria F.; Borrego, Belen; Brocchi, Emiliana; Armas-Portela, Rosario; Sobrino, Francisco

    2008-01-01

    The intracellular distribution of swine vesicular disease virus (SVDV) proteins and the induced reorganization of endomembranes in IBRS-2 cells were analyzed. Fluorescence to new SVDV capsids appeared first upon infection, concentrated in perinuclear circular structures and colocalized to dsRNA. As in foot-and-mouth disease virus (FMDV)-infected cells, a vesicular pattern was predominantly found in later stages of SVDV capsid morphogenesis that colocalized with those of non-structural proteins 2C, 2BC and 3A. These results suggest that assembly of capsid proteins is associated to the replication complex. Confocal microscopy showed a decreased fluorescence to ER markers (calreticulin and protein disulfide isomerase), and disorganization of cis-Golgi gp74 and trans-Golgi caveolin-1 markers in SVDV- and FMDV-, but not in vesicular stomatitis virus (VSV)-infected cells. Electron microscopy of SVDV-infected cells at an early stage of infection revealed fragmented ER cisternae with expanded lumen and accumulation of large Golgi vesicles, suggesting alterations of vesicle traffic through Golgi compartments. At this early stage, FMDV induced different patterns of ER fragmentation and Golgi alterations. At later stages of SVDV cytopathology, cells showed a completely vacuolated cytoplasm containing vesicles of different sizes. Cell treatment with brefeldin A, which disrupts the Golgi complex, reduced SVDV (∼ 5 log) and VSV (∼ 4 log) titers, but did not affect FMDV growth. Thus, three viruses, which share target tissues and clinical signs in natural hosts, induce different intracellular effects in cultured cells

  2. Construction and characterization of a full-length infectious cDNA clone of foot-and-mouth disease virus strain O/JPN/2010 isolated in Japan in 2010.

    Science.gov (United States)

    Nishi, Tatsuya; Onozato, Hiroyuki; Ohashi, Seiichi; Fukai, Katsuhiko; Yamada, Manabu; Morioka, Kazuki; Kanno, Toru

    2016-06-01

    A full-length infectious cDNA clone of the genome of a foot-and-mouth disease virus isolated from the 2010 epidemic in Japan was constructed and designated pSVL-f02. Transfection of Cos-7 or IBRS-2 cells with this clone allowed the recovery of infectious virus. The recovered virus had the same in vitro characterization as the parental virus with regard to antigenicity in neutralization and indirect immunofluorescence tests, plaque size and one-step growth. Pigs were experimentally infected with the parental virus or the recombinant virus recovered from pSVL-f02 transfected cells. There were no significant differences in clinical signs or antibody responses between the two groups, and virus isolation and viral RNA detection from clinical samples were similar. Virus recovered from transfected cells therefore retained the in vitro characteristics and the in vivo pathogenicity of their parental strain. This cDNA clone should be a valuable tool to analyze determinants of pathogenicity and mechanisms of virus replication, and to develop genetically engineered vaccines against foot-and-mouth disease virus. Copyright © 2016 Elsevier Ltd. All rights reserved.

  3. A dominant negative mutant of rab5 inhibits infection of cells by foot-and-mouth disease virus; implications for virus entry

    DEFF Research Database (Denmark)

    Johns, Helen; Berryman, Stephen; Monaghan, Paul

    2009-01-01

    Foot-and-mouth disease virus (FMDV) can use a number of different integrins (alphavβ1, alphavβ3, alphavβ6, and alphavβ8) as receptors to initiate infection. Infection mediated by alphavβ6 is known to occur by clathrin-mediated endocytosis and is dependent on the acidic pH within endosomes....... On internalization, virus is detected rapidly in early endosomes (EE) and subsequently in perinuclear recycling endosomes (PNRE), but not in late endosomal compartments. Due to the extreme sensitivity of FMDV to acidic pH, it is thought that EE can provide a pH low enough for infection to occur; however, definitive...... proof that infection takes place from within these compartments is still lacking. Here we have investigated the intracellular transport steps required for FMDV infection of IBRS-2 cells, which express vβ8 as their FMDV receptor. These experiments confirmed that FMDV infection mediated by alphavβ8...

  4. Estimation of residual stress in cold rolled iron-disks from strain measurements on the high resolution Fourier diffractometer

    International Nuclear Information System (INIS)

    Aksenov, V.L.; Balagurov, A.M.; Taran, Yu.V.

    1995-01-01

    The results of estimating residual stresses in cold rolled iron disks by measurements with the high resolution Fourier diffractometer (HRFD) at the IBR-2 pulsed reactor are presented. These measurements were made for calibration of magnetic and ultrasonic measurements carried out at the Fraunhofer-Institute for Nondestructive Testing in Saarbrucken (Germany). The tested objects were cold rolled steel disks of 2.5 mm thickness and diameter of about 500 mm used for forming small, gas pressure tanks. Neutron diffraction experiments were carried out at the scattering angle 2θ=+152 d eg with resolution Δd/d=1.5·10 -3 . The gauge volume was chosen according to the magnetic measurements lateral resolution 20x20 mm 2 . In the nearest future the neutron diffraction measurements with cold rolled iron disks at the scattering angle 2θ=±90 0 are planned. Also the texture analysis will be included in the Rietveld refinement procedure for more correct calculation of residual stress fields in the cold rolled materials. 8 refs., 10 figs., 1 tab

  5. Anisotropic mobility and carrier dynamics in the β-type BEDT-TTF salts as studied by inter-layer transverse magnetoresistance

    Directory of Open Access Journals (Sweden)

    Shigeharu Sugawara and Masafumi Tamura

    2013-01-01

    Full Text Available A new method to estimate an in-plane conduction anisotropy in a quasi-two-dimensional (q2D layered conductor by measuring the inter-layer transverse magnetoresistance is proposed. We applied this method to layered organic conductors β-(BEDT-TTF2X (BEDT-TTF = bis(ethylenedithiotetrathiafulvalene, C10H8S8; X = IBr2, I2Br by applying magnetic field rotating within the basal plane at 4.2 K. We found the anisotropic behaviour of carrier mobility μ. From this, anomalous distribution of carrier lifetime τ on the Fermi surface is derived, by the use of Fermi surface data reported for the materials. Calculations of the non-uniform susceptibility χ0(q suggest that carrier scattering is enhanced at specific k-points related to partial nesting of the Fermi surface. The present method is thus demonstrated to be an efficient experimental tool to elucidate anisotropic carrier dynamics in q2D conductors.

  6. Application Of NAA And AAS In Environmental Research In Slovakia

    International Nuclear Information System (INIS)

    Florek, M.; Holy, K.; Meresova, J.; Sykora, I.; Frontasveva, M. V.; Ermakova, E.E.; Pavlov, S.S.; Mankovska, B.

    2007-01-01

    The concentrations of 41 chemical elements (heavy metals, rare earths, and actinides) were determined in atmospheric aerosol using nuclear and related analytical techniques. The sampling location was in Bratislava (Slovak Republic). The main goal of this study is the quantification of the atmospheric pollution and its trend. The elemental content in filters was measured using instrumental neutron activation analysis (NAA) at IBR-2 reactor in JINR Dubna and by atomic absorption spectrometry (AAS) in Bratislava. The obtained results confirm the decreasing trend of pollution by most of the heavy metals in Bratislava atmosphere, and they are compared with the contents of pollutants in atmosphere of other cities, including Cairo. We determined also the composition of clear filter materials. Results on atmospheric deposition of heavy metals and other trace elements in the whole territory Slovakia using the moss bio monitoring technique are presented, too. The level of the elements found in the bryophytes reflects the relative atmospheric deposition loads of the elements at the investigated sites. Factor analysis was applied to determine possible sources of trace element deposition in the Slovakian moss. The marginal hot spots were revealed near nonferrous ores processing and factories and dumps of stone chips. The trans-boundary contamination by Hg through dry and wet deposition from Czech Republic and Polish is evident in the bordering territory in the north-west part of Slovakia (The Small Black Triangle), known for metallurgical works, coal processing and chemical industries

  7. Neutron diffraction study of structural changes in ammonium halides ND4Br and ND4Cl under high pressure

    International Nuclear Information System (INIS)

    Balagurov, A.M.; Kozlenko, D.P.; Savenko, B.N.; Glazkov, V.P.; Somenkov, V.A.

    1997-01-01

    Structural changes in ammonium halides ND 4 Br and ND 4 Cl at pressures up to 45 kbar and up to 35 kbar, respectively, have been studied with the DN-12 diffractometer at the IBR-2 pulsed reactor. For both systems, the equation of state and the position parameter of deuterium atoms as functions of pressure were obtained. The obtained equations of state are nearly the same as the ones for the nondeuterated systems NH 4 Br and NH 4 Cl obtained by the piston displacement technique. It was found that the order - disorder phase transition from the phase in which the ammonium tetrahedra are randomly oriented (CsCl-type cubic structure, space group Pm3m) into the phase in which the ammonium tetrahedra are oriented in parallel (CsCl-type cubic structure, space group P4 bar 3m), occurs at equal critical value of the position parameter u=0.153 ± 0.002 in both systems. It appears to be valid for all of the ammonium halides, and, possibly, for other similar compounds. (author)

  8. Testing an ionization chamber with gaseous samples and measurements of the (n, alpha) reaction cross sections

    CERN Document Server

    Gledenov, Yu M; Salatskii, V I; Sedyshev, P V; Andrzejewski, J; Szalanski, P

    1999-01-01

    A new ionization chamber with gaseous samples (GIC) has been designed and tested on the thermal and resonance neutron beams of FLNP's neutron sources. The exposed gas volume serves as a target for neutrons. The obtained thermal cross sections for the sup 1 sup 7 O(n, alpha) sup 1 sup 4 C, sup 2 sup 1 Ne(n, alpha) sup 1 sup 8 O and sup 3 sup 6 Ar(n, alpha) sup 3 sup 3 S reactions are (233+-12) mb, (0.18+-0.09) mb and (5.43+-0.27) mb, respectively. These measurements have been performed on a pure beam of thermal neutrons from the high flux reactor IBR-2; and they demonstrated high efficiency and reliability of the method. Compared to samples on substrates, the application of gaseous samples makes the beam background essentially lower, and what is more important, the background component is totally absent due to the absence of Li and B microimpurities in gaseous samples while they do present in the samples on substrates. The method is also applicable to measurements with resonance neutrons. The recovery capabili...

  9. Metal Hall sensors for the new generation fusion reactors of DEMO scale

    Science.gov (United States)

    Bolshakova, I.; Bulavin, M.; Kargin, N.; Kost, Ya.; Kuech, T.; Kulikov, S.; Radishevskiy, M.; Shurygin, F.; Strikhanov, M.; Vasil'evskii, I.; Vasyliev, A.

    2017-11-01

    For the first time, the results of on-line testing of metal Hall sensors based on nano-thickness (50-70) nm gold films, which was conducted under irradiation by high-energy neutrons up to the high fluences of 1 · 1024 n · m-2, are presented. The testing has been carried out in the IBR-2 fast pulsed reactor in the neutron flux with the intensity of 1.5 · 1017 n · m-2 · s-1 at the Joint Institute for Nuclear Research. The energy spectrum of neutron flux was very close to that expected for the ex-vessel sensors locations in the ITER experimental reactor. The magnetic field sensitivity of the gold sensors was stable within the whole fluence range under research. Also, sensitivity values at the start and at the end of irradiation session were equal within the measurement error (<1%). The results obtained make it possible to recommend gold sensors for magnetic diagnostics in the new generation fusion reactors of DEMO scale.

  10. 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

  11. Study of α-crystallin structure by small-angle neutron scattering with contrast variation

    International Nuclear Information System (INIS)

    Krivandin, A.V.; Muranov, K.O.; Polyanskij, N.B.; Ostrovskij, M.A.; Murugova, T.N.; Kuklin, A.I.; Aksenov, V.L.

    2010-01-01

    The structure of the oligomeric protein α-crystallin from the bovine eye lens has been investigated by small-angle neutron scattering (SANS) by the contrast variation method (volume fraction of D 2 O was 0, 23, 68 and 90%). Experiments were carried out on YuMO spectrometer (IBR-2 reactor, JINR). From the SANS curves the match point for α-crystallin (43% D 2 O) and its average scattering length density at this point (2.4·10 10 cm -2 ) have been obtained. The radius of gyration and distance distribution functions for α-crystallin have been calculated as well. On the basis of these calculations it was concluded that α-crystallin has a homogeneous distribution of the scattering density in domains inaccessible for water penetration and all parts of this protein undergo a uniform deuteration. The latter indicates that all α-crystallin subunits have an equal accessibility for water and presumably for some other low molecular weight substances. These conclusions on the α-crystallin structure (a homogeneous distribution of the scattering density and an equal accessibility of all subunits for low molecular weight substances) should be taken into account in the time of elaboration of α-crystallin quaternary structure models

  12. Life sciences research at JINR, Dubna, Russia

    International Nuclear Information System (INIS)

    Frontasyeva, M.V.

    2007-01-01

    Within the broad spectrum of activities in the Life Sciences at JINR such as nuclear medicine and pharmacy, radiation biology, radioecology, radioisotope production radioanalytical investigations play a special role due to the long-term experience in multi-element instrumental neutron activation analysis (INAA) at the reactor IBR-2 of FLNP, JINR. INAA is presently being used in several projects on air pollution studies using bio monitors (moss, lichens, tree bark). The results for some selected areas of Central Russia, South Urals, and countries of Europe (Bulgaria, Poland, Romania, Bosnia and Herzegovina, Serbia and Montenegro, Macedonia, Slovakia, Western Ukraine) are reported to the European Atlas of Heavy Metal Atmospheric Deposition edited under the auspices of the Environmental Commission of the United Nations. Battering-ram studies using NAA were initiated also in Turkey, China and South Korea. Applied to the analysis of air filters, INAA is successfully used in assessing quality of London underground air, Sahara desert impact on the Greater Cairo Area. Epithermal activation analysis in combination with atomic absorption spectrometry and energy-disperse X-ray fluorescence allowed source evaluation of metals in soil from some industrial and metropolitan areas of Russia (South Urals, Cola Peninsula) and the USA (Minneapolis). The analytical possibilities of NAA are favorably used in biotechnology, (i) for investigation of bacterial leaching of metals, including uranium and thorium from low-grade ores, rocks and industrial wastes; (i i) in the development of new pharmaceuticals based on the blue-green alga Spirulina platensis. Occupational health studies are carried out at several fertilizer plants in Russia, Uzbekistan, Poland, Romania, Denmark and the Netherlands in the framework of the 5th Programme Copernicus. The quality of foodstuffs grown in some contaminated areas of Russia is investigated in the framework of IAEA Coordinated Research Programme. In

  13. Neutron, gamma and Roentgen fluorescent activation analysis of hair of children suffering from bronchial asthma

    International Nuclear Information System (INIS)

    Alekseeva, O.A.; Belov, A.G.; Frontasyeva, M.V.; Gundorina, S.F.; Gustova, M.V.; Kusmenko, L.G.; Perelygin, V.P.; Zaverioukha, O.S.

    2001-01-01

    The aim of present study was the multiparametric study of dangerous microelements content in the hair of children under school and primary school age which included 12 children ill with bronchial asthma and 11 control group persons in the town of Troitsk, Moscow Region. The hair specimens with weight 15-220 mg were analysed with the application of epithermal neutron activation analysis conducted at experimental installation REGATA and neutron source-unique Pulsed Fast Reactor IBR-2, with the application of combined gamma-neutron irradiation at Microtron MT-25 and with Roentgen Fluorescence Analysis device of JINR. The data of elements content in hair were obtained with solid state track detectors and semiconductor electronic spectrometers. The solid state track detectors provide the determination of U, Th, Bi and Be elements at the level of sensitivity up to 10 -8 -10 -9 g/g. These data were compared with more representative information about dangerous microelements concentration obtained with NAA and RFA analyses. The obtained concentrations of most elements vary in a wide range, but in agreement with the known data. The highest degree of element dispersion was observed for U, Th, Pb, I, Br, Sb, Co, K and Be (the radiation coefficient was higher than 100-200%). The presented analysis of results shows that in the clinical picture there is some proved correlation between an increased content of some element in hair and symptoms of their accumulation in the organism of ill children, the revelation of which is the basic idea of our examination

  14. Active moss biomonitoring applied to an industrial area in Romania: variation of element contents with the height of exposure site

    International Nuclear Information System (INIS)

    Culicov, O.; Yurukova, L.; Mocanu, R.; Frontasyeva, V.; Sarbu, C.

    2007-01-01

    Neutron activation analysis and the moss-bag transplant technique were used to investigate the variation of element contents with the height of the exposure site of Sphagnum girgensohnii samples in the strongly polluted town of Baia Mare, Romania, according to a novel sampling design. Moss collected from the background area in Moscow region, Russia, was hanged in bags at 3 locations spread within an area of one square kilometre, and analyzed after 4 months of exposure. At each location a number of 15 samples were suspended at 6 different levels above the ground: 6, 12, 18, 24 and 30 m. A total of 35 elements were determined by NAA at IBR-2 reactor in Dubna, Russia. Discriminant Analysis allowed depicting the differences between the accumulation patterns of moss at different levels of exposure and at various locations. The concentration of only twenty four and twenty five elements of thirty five provided sufficient information to enable classification rules to be developed for identifying moss samples according with their height of exposure and location, respectively. The most discriminant elements have the F values (indicating the statistical significance in the discrimination between groups) descending in the following order: K, Rb, Sb, Cs, Zn, Cl for the location model and Ca, Cd, As, Sr, Ba, Cl for the height model. A good agreement have been observed between the groups obtained by applying Discriminant Analysis and the origin of the samples. A small number of elements are significant for the separation of moss-bags by height in individual locations. The parameter ?variation in concentration by height? is less significant than the parameter ? variation in concentration by location?

  15. Biomonitoring air pollution in Chelyabinsk region (Ural mountains, Russia) through trace-elements and radionuclides: Temporal and spatial trends

    International Nuclear Information System (INIS)

    Cherchintsev, V.D.; Frontasyeva, M.V.; Lyapunov, S.M.; Smirnov, L.I.

    1999-01-01

    This report contains the first results on the analysis of the moss species Hylocomium splendens and Pleurozium schreberi which were used to study heavy metal atmospheric deposition in the vicinity of Magnitogorsk, the center of the iron steel industry of Russia. Moss samples were collected along Bannoe Lake, located 30 km north-west of Magnitogorsk, and were analyzed by instrumental neutron activation analysis using epithernal neutrons (ENAA) at the IBR-2 pulsed fast reactor in Dubna, and by atomic absorption spectroscopy (AAS) at the Geological Institute of RAS, Moscow. Results for a total of 38 elements were obtained, including Pb, Cd, and Cu determined by AAS. The element concentrations in moss samples from this area were compared with those available for the so-called 'Black Triangle' (the territory bordering Poland, Czechia and Slovakia), obtained by the same moss biomonitoring technique. The level of the concentrations of Fe, Cr, and V in the vicinity of Magnitogorsk was found to be 2-2.5 times higher than that of the mean values determined for the 'Black Triangle'; the level of Ni and Cd is of the same order as in the most polluted area of Europe. The concentrations of Zn and Cu tend to be higher in the 'Black Triangle'. The level of As is about 3 times higher in the Urals, whereas concentration of Pb is higher in Europe by a factor of 5. It appeared that concentration of Sb in the examined area has the highest ever published for levels in mosses from atmospheric deposition. The scanning electron microscope adjacent to the XRF analyzer (SEM-XRF) was used to examine the surface of the moss samples. Photographs of identified iron spherulas along with other aerosol particles were made at magnification of 3,500 to 5,000 times. Information on fieldwork in the northern part of the Chelyabinsk region in July, 1998 is reported. (author)

  16. A pilot study of the selenium content in the soils of the endemic Dobrogea region, Romania, using nuclear and related analytical techniques

    International Nuclear Information System (INIS)

    Tripadus, V.; Craciun, L.; Lacatusu, R.; Frontasyeva, M.V.; Stan, O.; Lyapunov, S.M.

    2000-01-01

    At present, there is growing interest in the understanding of the role of selenium in human and animal metabolism. Selenium is known to be a normal component of several enzymes, proteins and some aminoacrylic transfer nucleic acids. Low levels of selenium intake are reported to cause diseases such as cardiomyopathy (Keshan disease), cancer and endemic osteoarthropathy characterized by necrosis of cartilage and dystrophy of skeletal muscles (Kaschin-Beck disease). In conjunction with the vitamin E, it removes free radicals from the living organisms. About two-to-three orders of magnitude higher levels of selenium are known to impart toxic effects. The Dobrogea Region in Romania is known for endemic cardiovascular diseases affecting domestic cattle, mostly sheep and milk cows. Soil, being the source of selenium, is responsible for its content in the whole trophic chain. A limited number of soil samples collected in the pastures (Dobrogea) were subject to epithermal neutron activation analysis at the IBR-2 pulsed fast reactor in Dubna, Russia. To verify the obtained results, the same samples were analyzed by the fluorescent extraction method, especially efficient for determination of selenium at low concentrations, at the Geological Institute of RAS in Moscow, Russia. The mean concentration of selenium was found to be equal to 0.38 ppm with a standard deviation of 0.13. The accuracy of the selenium determination was not worse than 20%. These preliminary results are not evidence of obvious selenium deficiency, however. A systematic study on a large geographical scale is strongly recommended to elucidate the problem of cattle morbidity in the examined area. (authors)

  17. Small-Angle Neutron Scattering investigations of ferrofluids with different carrier liquids

    International Nuclear Information System (INIS)

    Balasoiu, M.; Avdeev, M. V.; Hasegan, D.; Ghenescu, V.; Ghenescu, M.; Bica, D.; Vekas, L.

    2004-01-01

    The aim of this paper is to present a method to investigate the properties of magnetic fluids by means of small angle neutron scattering (SANS). Ferrofluids are dispersions of small, single-domain magnetic particles suspended in a fluid carrier. The neutron scattering methods have been largely used the last two decades for the determination of structural properties of magnetic liquids at microscopic level. There can be investigated the structure of the particle, the aggregation phenomena, the magnetic liquid dynamics, particle-surfactant interaction, surfactant liquid-base interaction and structure and magnetic behavior of the samples. SANS is often used in structural studies of ferrofluids exploring two specific features of neutrons, the possibility of wide contrast variation using protonated/deuterated components and high magnetic scattering from ferromagnetics. This method can be effectively used for determination of the structural parameters of ferrofluids at the scale interval of 1-100 nm. In previous SANS experiments with ferrofluids of the same type it was shown that the nuclear scattering is described well by the spherical core-shell model (magnetite core plus surfactant shell) in a wide interval of momentum transfer (0.05 - 5 nm -1 ) and no significant effects of aggregation and interparticle interaction were observed in this interval for the magnetite concentration up to 5 vol. %. Experiments on small angle neutron scattering were carried out on SANS instrument YuMO in function at IBR-2 high pulsed reactor at the Frank Laboratory of Neutron Physics, Joint Institute of Nuclear Research, Dubna, Russia. (authors)

  18. Epithermal Neutron Activation Analysis of the Asian Herbal Plants

    International Nuclear Information System (INIS)

    Baljinnyam, N.; Frontasyeva, M. V.; Ostrovnaya, T. M.; Pavlov, S. S.; Jugder, B.; Norov, N.

    2011-01-01

    Asian medicinal herbs Chrysanthemum (Spiraea aquilegifolia Pall.) and Red Sandalwood (Pterocarpus Santalinus) are widely used in folk and Ayurvedic medicine for healing and preventing some diseases. The modern medical science has proved that the Chrysanthemum (Spiraea aquilegifolia Pall.) possesses the following functions: reducing blood press, dispelling cancer cell, coronary artery's expanding and bacteriostating and Red Sandalwood (Pterocarpus Santalinus) is recommended against headache, toothache, skin diseases, vomiting and sometimes it is taken for treatment of diabetes. Species of Chrysanthemums were collected in the north-eastern and central Mongolia, and the Red Sandalwood powder was imported from India. Samples of Chrysanthemums (branches, flowers and leaves)(0.5 g) and red sandalwood powder (0.5 g) were subjected to the multi-element instrumental neutron activation analysis using epithermal neutrons (ENAA) at the IBR-2 reactor, Frank Laboratory of Neutron Physics (FLNP) JINR, Dubna. A total of 41 elements (Na, Mg, Al, Cl, K, Ca, Sc, V, Cr, Mn, Fe, Co, Ni, Zn, As, Se, Br, Rb, Sr, Zr, Mo, Cd, Cs, Ba, La, Hf, Ta, W, Sb, Au, Hg, Ce, Nd, Sm, Eu, Tb, Dy, Yb, Th, U, Lu) were determined. For the first time such a large group of elements was determined in the herbal plants used in Mongolia. The quality control of the analytical results was provided by using certified reference material Bowen Cabbage. The results obtained are compared to the ''Reference plant? data (B. Markert, 1992) and interpreted in terms of excess of such elements as Se, Cr, Ca, Fe, Ni, Mo, and rare earth elements.

  19. ICANS-XIV. The fourteenth meeting of the international collaboration on advanced neutron sources

    International Nuclear Information System (INIS)

    Carpenter, J. M.; Tobin, C. A.

    1999-01-01

    The meeting began with a reception on Sunday evening. Monday's plenary sessions included status reports on the four operating spallation neutron sources, IPNS, ISIS, KENS, and the Lujan Center; on the INR source under construction at Troitsk; on the IBR-2 pulsed reactor at Dubna; and on proposals for five new installations. We also heard reports on spin-off activities: the ASTE tests (liquid mercury target tests at the AGS accelerator at Brookhaven), the ACoM activities (developments aimed to provide cold moderators suitable for high-power pulsed sources), and the International Workshop on Cold Moderators for Pulsed Neutron Sources, held in September 1997 at Argonne. Jose Alonso and Bob Macek delivered enlightening invited talks overviewing linear accelerators and rings for spallation neutron sources. The rest of the meeting was devoted to targets and moderators and to instrumentation in a normal rotation of ICANS topics. There were altogether 84 oral reports and 23 poster presentations. On Tuesday and on Wednesday morning, we divided into separate series of sessions on Instrumentation and on Targets and Moderators. In the first, we had reports and discussions on instrumentation and techniques, on computer software, on instrument suites, and on new instruments and equipment. In the second series were sessions on liquid target systems, on solid target systems, on neutron production and target physics, on moderator physics and performance, and on target and moderator neutronics. The Tuesday evening meetings went on until 10:00, making for a 14-hour working day. That everyone willingly endured the long hours is a credit to the dedication of the attendees. On Wednesday afternoon, we boarded buses for the 1-hour trip to Argonne, where attendees toured IPNS and the Advanced Photon Source. Returning to Starved Rock, we enjoyed boat rides on the Illinois River and then a barbecue banquet dinner at the Lodge. All day Thursday and Friday morning, the attendees, in small

  20. T135I substitution in the nonstructural protein 2C enhances foot-and-mouth disease virus replication.

    Science.gov (United States)

    Yuan, Tiangang; Wang, Haiwei; Li, Chen; Yang, Decheng; Zhou, Guohui; Yu, Li

    2017-12-01

    The foot-and-mouth disease virus (FMDV) nonstructural protein 3A plays an important role in viral replication, virulence, and host range. It has been shown that deletions of 10 or 19-20 amino acids in the C-terminal half of 3A attenuate serotype O and C FMDVs, which replicate poorly in bovine cells but normally in porcine-derived cells, and the C-terminal half of 3A is not essential for serotype Asia1 FMDV replication in BHK-21 cells. In this study, we constructed a 3A deletion FMDV mutant based on a serotype O FMDV, the wild-type virus O/YS/CHA/05, with a 60-amino acid deletion in the 3A protein sequence, between residues 84 and 143. The rescued virus O/YS/CHA/05-Δ3A exhibited slower growth kinetics and formed smaller plaques compared to O/YS/CHA/05 in both BHK-21 and IBRS-2 cells, indicating that the 60-amino acid deletion in the 3A protein impaired FMDV replication. After 14 passages in BHK-21 cells, the replication capacity of the passaged virus O/YS/CHA/05-Δ3A-P14 returned to a level similar to the wild-type virus, suggesting that amino acid substitutions responsible for the enhanced replication capacity occurred in the genome of O/YS/CHA/05-Δ3A-P14. By sequence analysis, two amino acid substitutions, P153L in VP1 and T135I in 2C, were found in the O/YS/CHA/05-Δ3A-P14 genome compared to the O/YS/CHA/05-Δ3A genome. Subsequently, the amino acid substitutions VP1 P153L and 2C T135I were separately introduced into O/YS/CHA/05-Δ3A to rescue mutant viruses for examining their growth kinetics. Results showed that the 2C T135I instead of the VP1 P153L enhanced the virus replication capacity. The 2C T135I substitution also improved the replication of the wild-type virus, indicating that the effect of 2C T135I substitution on FMDV replication is not associated with the 3A deletion. Furthermore, our results showed that the T135I substitution in the nonstructural protein 2C enhanced O/YS/CHA/05 replication through promoting viral RNA synthesis.

  1. Neutron Tests at the Start-Up of EDF1; Les essais neutroniques au demarrage du reacteur EDF1; Nejtronnye izmereniya pri puske reaktora EDF1; Ensayos neutronicos efectuados durante la puesta en marcha del reactor EDF1

    Energy Technology Data Exchange (ETDEWEB)

    Teste du Bailler, A. [Centre d' Etudes Nucleaires de Saclay (France); Janin, R. [Electricite de France, Paris (France)

    1963-10-15

    ehksperimental'nykh metodov, razrabotannykh na reaktorakh v Markule, byla provedena vo vremya puska reaktora EDF.1. Izmereniya kasalis' glavnym obrazom ehffektivnosti upravlyayushchikh sterzhnej pri razlichnykh p ogruzh eniyakh. Opredelyaetsya skhema pod''ema s terzhnej, kotoraya pozvolyaet poluchat' polnuyu moshchnost' prk soblyudenii opredelennykh ogranichenij v temperature obolochek i gaza. Parallel'no byli provedeny izmereniya potoka pri razlichnykh polozheniyakh kompensiruyushchikh sterzhnej i pri razlichnykh zagruzkakh poglotitelej v opredelennykh kanalakh, v zavisimosti ot predvaritel'nykh raschetov v dvukhraehmernom izmerenii. Ehti izmereniya byli polucheny putem aktivatsii tochechnykh detektorov s primeneniem obychnogo metoda otravleniya vozdukha. Pri nekotorykh urovnyakh temperatury (do 140{sup o}C) byli provedeny izmereniya koehffitsientov reaktivnosti i ehffektivnosti reguliruyushchikh sterzhnej. V to zhe vremya putem aktivatsii sootvetstvuyushchikh detektorov (uran, plutonij, lyutetsij, marganets, indij, zoloto) byli provedeny izmereniya koehffitsientov spektra. Dlya izmereniya ehffektivnosti nekotorykh kompensiruyushchikh sterzhnej byl ispol'zovan ostsillyatsionnyj metod. Nakonets, s tselyakh izucheniya zashchity i povrezhdeniya grafita byli provedeny izmereniya potoka bystrykh nejtronov. (author)

  2. Selected Abstracts of the 2nd Congress of joint European Neonatal Societies (jENS 2017; Venice (Italy; October 31-November 4, 2017; Session "Neonatal Hematology and Bilirubin"

    Directory of Open Access Journals (Sweden)

    --- Various Authors

    2017-10-01

    Full Text Available Selected Abstracts of the 2nd Congress of joint European Neonatal Societies (jENS 2017; Venice (Italy; October 31-November 4, 201758th ESPR Annual Meeting, 7th International Congress of UENPS, 3rd International Congress of EFCNIORGANIZING INSTITUTIONSEuropean Society for Paediatric Research (ESPR, European Society for Neonatology (ESN, Union of European Neonatal & Perinatal Societies (UENPS, European Foundation for the Care of Newborn Infants (EFCNIORGANIZING COMMITTEELuc Zimmermann (President of ESPR, Morten Breindahl (President of ESN, Manuel Sánchez Luna (President of UENPS, Silke Mader (Chairwoman of the Executive Board and Co-Founder of EFCNISCIENTIFIC COMMITTEEVirgilio P. Carnielli (Congress President Chair, Pierre Gressens (Past Scientific President, Umberto Simeoni, Manon Benders, Neil Marlow, Ola D. Saugstad, Petra Hüppi, Agnes van den HoogenSession "Neonatal Hematology and Bilirubin"ABS 1. PROLONGED JAUNDICE SCREENING: FULL BLOOD COUNT (FBC OR NO FBC! • N. Storring, R. Doherty, V. PonnusamyABS 2. EFFECT OF PROBIOTIC SUPPLEMENTATION ON BREAST MILK JAUNDICE • N. Koksal, O. Bagcı, H. Ozkan, I. Varal, P. DoganABS 3. LABORATORY FINDINGS, DIAGNOSIS AND TREATMENT OF THE NEWBORN ADMITTED DUE TO HEMATEMESIS OR BLOODY STOOL IN 11 YEARS • I. Hokuto, Y. Ito, T. Mori, S. KomachiABS 4. AN UNUSUAL CAUSE OF CYANOSIS: SEVERE METHEMOGLOBINEMIA IN A PRETERM INFANT WITH SEPSIS • F. Bakar, M. BerberABS 5. THE INFLUENCE OF INTRAUTERINE TRANSFUSION ON THE OUTCOMES OF NEWBORNS WITH SEVERE HEMOLYTIC DISEASE • E. Balashova, O. Bystrykh, T. Fedorova, O. Ionov, A. Kirtbaya, D. Sharafutdinova, V. Zubkov, D. Degtyarev, O. Horoshkeeva, N. Fedorova, N. Tetruashvili, K. Kostukov, N. KaretnikovaABS 6. PATCHED SKIN BILIRUBIN ASSAY TO MONITOR EXTREMELY PRETERM NEONATES UNDERGOING PHOTOTHERAPY • D. De Luca, V. Dell’OrtoABS 7. A PRETERM MODEL OF HYPERBILIRUBINEMIA-INDUCED CEREBELLAR DYSFUNCTION • C.F. Bearer, M. He, J.F. Watchko, J.M. Simard, N. Tang

  3. Amplitude-measuring devices for electric pulses in the nanosecond region; Dispositifs de mesure d'amplitude d'impulsions electriques dans le domaine de la nanoseconde; Pribory dlya izmereniya amplitudy ehlektricheskikh impul'sov v sfere nanosekundy; Dispositivos para medir la amplitud de los impulsos electricos en la region del nanosegundo

    Energy Technology Data Exchange (ETDEWEB)

    Samueli, J J; Sarazin, A [Institut d' Etudes Nucleaires d' Alger (France)

    1962-04-15

    amplitud maxima de impulsos rapidos. En general, estos circuitos deben poder dar una indicacion independiente, de ser posible, de la duracion y de la forma de la senal estudiada. El primer circuito es un alargador de impulsos, es decir un aparato que transforma las senales rapidas en impulsos de duracion constante y de amplitud proporcional a la amplitud inicial, y que, por tanto, permite estudiar las senales rapidas con un selector de amplitudes convencional. El circuito admite senales de duracion superior a 2 ns y de amplitud comprendida entre 1 y 15 V. Emite dos senales de duracion constante de 100 ns y de 1 {mu}s. El segundo circuito es un discriminador de amplitudes rapido, de umbral graduable entre 1 y 30 V y cuya desviacion de lectura para impulsos de 100 y de 2 ns de duracion es del orden de 18%. La senal de salida tiene una amplitud de 1,5 V y una duracion standard de 0,2 {mu}s. (author) [Russian] Daetsya opisanie dvukh ehlektronnykh priborov, dayushchikh vozmozhnost' proizvodit' izmerenie maksimal'noj amplitudy bystrykh impul'sov. V obshchem ot ehtikh priborov trebuyut predostavleniya, po vozmozhnosti, nezavisimoj indikatsii dlitel'nosti i formy izuchaemogo signala. Pervyj pribor predstavlyaet soboj rasshiritel' impul'sov, t.e ustanovku, kotoraya preobrazuet bystrye signaly v impul'sy postoyannoj shiriny i proportsional'noj amplitudy po sravneniyu s nuzhnoj amplitudoj i kotoraya poehtomu pozvolit izuchit' bystrye signaly pri pomoshchi obychnogo amplitudnogo selektora. Pribor prinimaet signaly shirinoj svyshe dvukh nanosekund, a amplituda kolebletsya mezhdu odnoj i 15 vol'tami. On daet dva signala postoyannoj shiriny v 100 nanosekund i v 1 {mu}s. Vtoroj pribor predstavlyaet iz sebya bystryj amplitudnyj diskriminator s reguliruyushchim porogom ot 1 do 30 vol't, i otschetnoe otklonenie kotorogo dlya impul'sov shirinoj v 100 i dve nanosekundy sostavlyaet 18%. Vykhodnoj signal imeet amplitudu v poltora vol'ta i standartnuyu shirinu v 0,2 {mu}s. (author)

  4. The epithermal critical experiments; Experiences critiques avec des neutrons epitliermiques; Nadteplovye kriticheskie ehksperimenty; Experimentos criticos con neutrones epitermicos

    Energy Technology Data Exchange (ETDEWEB)

    Morewitz, H A; Carpenter, S O [Atomics International, Canoga Park, CA (United States)

    1962-03-15

    provistos de detectores calibrados, de umbrales diferentes, y con un espectrometro en 'emparedado' de contador de {sup 6}Li solido. Se utilizara una calculador a numerica corriente para agrupar todas las mediciones en un registro sistematico de secciones eficaces promediadas respecto del espectro. (author) [Russian] Sovremennaya faza programmy issledovanij usovershenstvovannog o nadteplovogo torievogo reaktora sostoit iz polnykh ehksperimen- tov po reaktornoj fizike, provodimykh s tsel'yu obespecheniya informatsiej po nejtronnym secheniyam v diapazone ot 10 Mehv do 1 kehv. Izuchaetsya gruppa devyati mnogozonal'nykh , medlenno-bystrykh , psevdosfericheski kh kriticheskikh sborok 'KHanikouma' s dvumya podvizhnymi polovinami aktivnoj zony. K nastoyashchemu vremeni ispytany tri sborki. Vneshnyaya peremeshchayushchayas ya zona dvigaetsya po otnosheniyu k vnutrennej sfericheskoj ehksperimental'noj aktivnoj zone na urane-233 - torii, spektor nejtronnogo potoka kotoroj uspeshno smyagchaetsya uvelicheniem otnosheniya grafitovogo zamedlitelya k toplivu. EHksperiment s generatorom pryamougol'nykh impul'sov opredelit tsentral'nuyu reaktivnuyu sposobnost' soroka malykh obraztsov razlichnykh materialov do 10{sup -8} {Delta}k dlya kazhdoj sborki. Krome togo, vzaimno kalibrovannye iskusstvennye istochniki nejtronov ostsilliruyutsya v tselyakh opredeleniya razlichnykh funktsij tsentral'nogo nejtronnogo znacheniya. Spektry poluchayut putem izmerenij schetchikom deleniya s pomoshch'yu kalibrovannoj fol'gi razlichnykh porogov, a takzhe putem ispol'zovaniya schetnogo sloistogo spektrometra s L{sup 6} v tverdom sostoyanii. Dlya sbora vsekh izmerenij v samosoglasovannu yu biblioteku spektral'nykh srednikh poperechnykh sechenij budut pol'zovat'sya odnoznachnym vychislitel'nym rezhimom. (author)

  5. Current tendencies and perspectives of development research reactors of Russia

    International Nuclear Information System (INIS)

    Gabaraev, B.A.; Kchmelschikov, V.V.

    2004-01-01

    Full text: During more than fifty years many Research Reactors were constructed under Russian projects, and that is a considerable contribution to the world reactor building. The designs of Research Reactors, constructed under Russian projects, appeared to be so successful, that permitted to raise capacity and widen the range of their application. The majority of Russian Research Reactors being middle-aged are far from having their designed resources exhausted and are kept on the intensive run still. In 2000 'Strategy of nuclear power development in Russia in the first half of XXI century' was elaborated and approved. The national nuclear power requirements and possible ways of its development determined in this document demanded to analyze the state of the research reactors base. The analysis results are presented in this report. The main conclusion consists in the following statement: on the one hand quantity and experimental potentialities of domestic Research Reactors are sufficient for the solution of reactor materials science tasks, and on the other hand the reconstruction and modernization appears to be the most preferable way of research reactors development for the near-term outlook. At present time the modernization and reconstruction works and works on extension of operational life of high-powered multipurpose MIR-M1, SM-3, IRV-1M, BOR-60, IVV-2M and others are conducted. There is support for the development of Research Reactors, intended for carrying out the fundamental investigations on the neutron beams. Toward this end the Government of Russia gives financial and professional support with a view to complete the reactor PIK construction in PINPh and the reactor IBR-2 modernization in JINR. In future prospect Research Reactors branch in Russia is to acquire the following trends: - limited number of existent scientific centers, based on the construction sites, with high flux materials testing research reactors, equipped with experimental facilities

  6. Current trends in and prospects for development of Russian research reactors

    International Nuclear Information System (INIS)

    Arkhangelsky, N.V.; Cherepnin, Yu.S.; Gabaraev, B.A.; Khmelshchikov, V.V.; Tretiyakov, I.T.

    2004-01-01

    Over more than fifty years, many research reactors were built to Russian designs both at home and abroad, which is a considerable contribution to the world reactor engineering. Russian research reactors proved to be successful to an extent that it was found possible to raise capacity and to extend the range of their application. Though having a fairly long operating record, the majority of Russian research reactors are far from the end of their service life and are still in active use. In 2000, the 'Strategy of nuclear power development in Russia in the first half of the 21 st century' was elaborated and approved. The requirements of national nuclear power and the possible ways of its development identified in this document called for assessing the existing research capabilities. The findings of such assessment are presented in this report. The main conclusion lies in the following. On the one hand, the number and experimental capabilities of domestic research reactors are sufficient for coping with the objectives of research in, and on the other hand, retrofitting and upgrading appear to be the most expedient way of managing the operation of research reactors in the near term. Activities are under way to upgrade and extend the service life of multipurpose reactors, such as MIR-M1, SM-3, IRV-1M, BOR-60, IVV-2M, and others. The Federal Agency of the Russian Federation for Atomic Energy (Rosatom) supports the development of reactors intended for fundamental research with the use of neutron beams. To this end, Rosatom renders financial and professional support with a view to complete the PIK reactor construction at PIYaF and the IBR-2 reactor upgrades at JINR. In a longer term, the development of research reactors in Russia is expected to have the following pattern: - a small number of high-flux testing reactors with up-to-date experimental facilities located on the sites of the existing research centers; - PIK reactor, catering to domestic and foreign needs for beam

  7. Current status and prospects of research reactors

    International Nuclear Information System (INIS)

    Gabaraev, A.B.; Cherepnin, Yu.S.; Tretyakov, I.T.; Khmelshikov, V.V.; Dollezhal, N.A.

    2009-01-01

    Full text: The first nuclear research reactors (RR) appeared in the 1940s. Their initial purpose was to provide knowledge of the main processes associated with neutron-induced nuclear reactions. Later, the rang of problems addressed expanded substantially. Besides fundamental research in the properties of matter, such reactors are successfully used for dealing with problems in the fields of materials science, nuclear engineering, medicine, isotope production, education, etc. Over the whole period of RR fleet growth, more than six hundred nuclear research facilities were built in 70 countries of the world. As of the end of 2008, the number of Russian research reactors in service was about 20% of the globally operating RR fleet. This paper discusses the current status of the world's RR fleet and describes the capabilities of the experimental reactor facilities existing in Russia. In the 21st century, research reactors will remain in demand to solve scientific and technological problems for innovative development of society. The emerging renaissance of nuclear power, the expanding RR uses for production of isotopes and other applications, the increase in the number of countries willing to use nuclear technologies in energy production, industry and science - all contribute to a rebirth of interest in research reactors. One of the ways to improve the experimental capabilities lies in radical upgrading of the reactor facilities with qualitative changes in the main neutronic characteristics of the core. The associated design approaches are illustrated with the example of the IBR-2M reactor at the JNRI in Dubna. The imperative need restricting the spread of nuclear threat leads us to give up using highly enriched uranium in most research reactors. Development of RR fuel with reduced enrichment in uranium has been one of the priority objectives of NIKIET for many years. This paper presents the latest results obtained along these lines, as applied to pool-type research

  8. Department of Structural Research - Overview

    International Nuclear Information System (INIS)

    Wasiutynski, T.

    2002-01-01

    at the Dubna IBR-2 reactor. As a part of a larger project undertaken with Institute for Energietekknik (Kjeller, Norway) the low energy excitations have been studied in a glass and in two crystalline phases of the glass-forming triphenyl phosphite. Results of investigations of the dynamics of the methyl groups in the crystalline phase of 1,3,5,-(CH 3 ) 3 C 6 H 3 have been used during a testing procedure of computer simulation of the molecular dynamics based on the quantum chemistry methods. Neutron scattering is also used to investigate properties of polymers: polymer electrolytes and blends. Deep inelastic (''Compton'') scattering was applied to find the relation between stretching of the samples and kinetic energy of particular nuclei (the method capable of detecting potential anharmonicity). Structural factors affecting polymer miscibility were further studied by polarized neutron scattering techniques. In this research we cooperate with the Open University, Oxford, UK. Our theoretical studies concern phase transitions in molecular crystals as well as general dynamical properties of anharmonic surfaces and other structural defects. For an isomorphous phase transitions in the mixture of the fullerenes C 70(1-x) C 60x the highly anisotropic pseudospin model has been proposed, which turned out to be equivalent to the Ising model with two states of different statistical weights. The prediction of a disordered low temperature crystal has been confirmed by the dilatometric data. Delayed differential equantions governing the propagation of waves through an anharmonic defect have been solved with the use of an analogous electric circuit. Similar equations have been proposed to explain the deviation of the Curie constants from their mean field approximation values due to anharmonic effects in the temperature range close to the phase transition. Magnetic investigations have been performed for a wide scope of materials. For ternary 4f - 4d, 5d intermetallic compounds

  9. III International Conference on Small Angle Neutron Scattering dedicated to the 80 anniversary of Yu.M. Ostanevich

    International Nuclear Information System (INIS)

    2017-01-01

    Preface “Among the many well-known fundamental and applied consequences of neutron discovery, one of the first was the emergence of structural neutron diffraction - one of the methods for studying the spatial structure of condensed matter at the atomic level. Investigating the dynamics of biological macromolecules by neutron diffraction methods is an area that is almost untouched. We believe that also in this direction one should expect rapid progress.” Yu.M.Ostanevich and I.N.Serdyuk Uspekhi Fizicheskih Nauk (1982) More than 30 years after Ostanevich and Serdyuk reviewed the then 50 years from the neutron discovery, we are happy to support their statement and prediction by reporting on the further progress in the field of neutron scattering research. Frank Laboratory of Neutron Physics has organized the III International Conference on Small Angle Neutron Scattering (YuMO2016) that was – not coincidently – dedicated to the 80th anniversary of Ostanevich. Yuriy Mechislavovich Ostanevich (1936–1992) has had a determinative and crucial contribution to the construction of spectrometers at the pulsed reactor IBR in Dubna, Russia. He contributed in particular to the development of time-of-flight small-angle neutron scattering (SANS) technique, and the selection of advanced scientific areas for its application. The SANS instrument at the IBR-2 reactor is called YuMO in his honour. The Ostanevich’s leadership and outstanding scientific achievements in SANS studies of polyelectrolytes, small molecules, fractals, metallic glasses, macromolecules, polymers, etc., were recognized also by a number of awards including the State Prize of the Russian Federation in 2000. To this end of course, we should not forget mentioning the contribution of close collaborators of Ostanevich: Laszlo Cser, Josef Plestil as well as Alexander Kunchenko, Vadim Bezzabotnov and Nikolay Gorski. The YuMO2016 conference focused on providing opportunities to discuss various possibilities of

  10. Experimental studies of some of the physical features of beryllium-moderated intermediate reactors; Etude experimentale de quelques particularites physiques des reacteurs a neutrons intermediaires, ralentis au beryllium; Ehksperimental'ny e issledovaniya nekotorykh fizicheskikh osobennostej promezhutochnykh reaktorov s berillievym zamedlitelem; Estudios experimentales de algunas caracteristicas fisicas de los reactores intermedios moderados con berilio

    Energy Technology Data Exchange (ETDEWEB)

    Lejpunskij, A I; Kuznetsov, V A; Artyukhov, G Ya; Mogil' ner, A I; Prokhorov, Yu A; Steklovski, V M; Chernov, L A [Akademiya Nauk, Moskva, Union of Soviet Socialist Republics (Russian Federation)

    1962-03-15

    la evaluacion de la eficacia de los cilindros compensadores giratorios distribuidos en el limite entre el cuerpo y el reflector. (author) [Russian] Doklad posvyashchen obzoru nekotorykh ehksperimen-tal'nykh rezul'tatov, poluchennykh na stende PF-4, prednaznachennom dlya detal'nogo issledovaniya fizicheskikh osobennostej reaktorov, rabotayushchikh na nejtronakh promezhutochnykh ehnergij. Aktivnye zony i otrazhateli razlichnykh kriticheskikh sborok predstavlyali soboj plotnuyu upakovku stal'nykh ili alyuminievykh trub, v kotorykh pomeshchalis' diski iz razlichnykh materialov. Kombinatsiya diskov urana (90%-nogo obogashcheniya) i zamedlyayushchikh materialov v razlichnoj proportsii, a takzhe vvedenie v otrazhatel' zamedlyayushchikh sloev razlichnoj tolshchiny, pozvolilo menyat' spektr nejtronov, proizvodyashchikh delenie, v ochen' shirokikh predelakh. V doklade privedeno opisanie stenda i ego otdel'nykh uzlov. Analiziruetsya sravnitel'naya ehffektivnost' vnutrennego i vneshnego zamedleniya dlya reaktorov s ochen'malym otnosheniem yader zamedlitelya i urana v aktivnoj zone. Ehksperimenty pokazyvayut, chto dazhe v sluchae tolstykh zamedlyayushchikh otrazhatelej maloe razbavlenie urana zamedlitelem (otnoshenie yader berilliya i urana-235 {partial_derivative}Be/{partial_derivative}U{sup 235}{approx_equal}1) privodit k vozrastaniyu kriticheskoj massy. Znachitel'noe mesto v doklade udeleno analizu geterogennykh ehffektov v promezhutochnykh reaktorakh. Pokazano, chto dlya reaktora s {partial_derivative}Be/{partial_derivative}U{sup 235}= 30+40, vysokoobogashchenny j uran v razlichnykh tolshchinakh ot 0,023 g/sm{sup 2} do 32 g/sm{sup 2} okazyvaet odinakovoe vliyanie na reaktiv-nost' sistemy. Analiziruyutsya prichiny, privodyashchie k kompensatsii ehffekta ehkranirovki nejtronnogo potoka tolstymi sloyami urana. V doklade privoditsya interesnyj fakt vozrastaniya ehffektivnosti urana vblizi po- gloshchayushchikh sterzhnej, ehksperimental'n o obnaruzhennyj v sbor kes {partial