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Sample records for neutrones por fision

  1. Ternary Fission of U{sup 235} by Resonance Neutrons; Fission Ternaire de {sup 235}U par des Neutrons de Resonance; 0422 0420 041e 0419 041d 041e 0415 0414 0415 041b 0415 041d 0418 0415 0423 0420 0410 041d 0410 -235 041d 0410 0420 0415 0417 041e 041d 0410 041d 0421 041d 042b 0425 041d 0415 0419 0422 0420 041e 041d 0410 0425 ; Fision Ternaria del {sup 235}U por Neutrones de Resonancia

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    Kvitek, I.; Popov, Ju. P.; Rjabov, Ju. V. [Ob' edinennyj Institut Jadernyh Issledovanij, Dubna, SSSR (Russian Federation)

    1965-07-15

    feuille d'aluminium) on a procede a une mesure pour laquelle le volume ou la particule a long parcours etait enregistree se trouvait protege par un filtre d'aluminium supplementaire de 1 mm d'epaisseur. Les resultats de experience montrent que le rapport encre les fissions ternaire et binaire de {sup 235}U ne subit pas les fortes variations signalees par d'autres auteurs. Au cours des mesures on n'a constate aucune irregularite dans le rapport entre les sections efficaces pour les energies de 0,1 a 0,2 eV. Les auteurs du memoire examinent l'influence eventuelle de la reaction (n, {alpha}) sur les resultats des experiences pour lesquelles on nTa pas eu recoure a la coincidence entre particules a long parcours et fragments de fission. (author) [Spanish] Recientemente se han publicado varios trabajos acerca de la existencia de una variacion considerable en la razon de la seccion eficaz de fision ternaria a la seccion eficaz de fision binaria para el {sup 235}U, al pasar de una resonancia neutronica a otra. Hasta la fecha los autores no han descubierto ninguna variacion de esa indole para el {sup 235}U ni para el {sup 239}Pu. En la presente memoria se presentan los resultados del estudio de la fision ternaria del {sup 235}U inducida por neutrones de 0,1 a 30 eV de enetgia. A diferencia de otros trabajos sobre fision ternaria del {sup 23}'5U, el suceso de fision ternaria se identifico por coincidencia de uno de los fragmentos de fision con una particula ligera de laigo alcance. Esto permitio separar las fisiones ternarias de la posible contribucion de la reaccion (n, ex). Las mediciones se efectuaron en el reactor pulsado de neutrones rapidos del Instituto Central de Investigaciones Nucleares, por el metodo del tiempo de vuelo. La trayectoria de vuelo era de 100 m, lo que permitia lograr un poder de resolucion de 0,6 {mu}s/m. Los fragmentos de fision y las particulas ligeras de largo alcance se registraron por medio de contadores de centelleo gaseosos, llenos de xenon a 2 atm

  2. Primary Distributions of Nuclear Charge for Fission-Fragment Masses 132, 134, 136 and 137 from Thermal Fission of U{sup 235}; Repartition Primaire de la Charge Nucleaire pour les Fragments de Masse 132, 134, 136 et 137, Provenant de la Fission de {sup 235}U par Neutrons Thermiques; 041f 0415 0420 0414 ; Distribuciones Primarias de las Cargas Nucleares de los Fragmentos de Masa 132, 134, 136 y 137, Resultantes de la Fision del {sup 235}U por Neutrones Termicos

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    Konecny, E.; Opower, H.; Guenther, H.; Goebel, H. [Physik-Department der Technischen Hochschule Muenchen, Munich and II. Physikalisches Institut der Justus Liebig-Universitaet Giessen, Federal Republic of Germany (Germany)

    1965-07-15

    = 82 que sont dues les charges primaires les plus probables voisines de 50 et 52 respectivement. Lorsque M = 136 ou 137, la charge primaire est d'environ 53 et 53,2. Il s'est revele que les corrections approximatives supplementaires pour tenir compte des electrons de conversion (en negligeant les traces {beta} tres courtes correspondant a des energies {beta} tres faibles) et des neutrons retardes (pour la masse 137) ne sont pas tres importantes. On prepare actuellement des mesures analogues qui seront effectuees directement dans une geometrie 4{pi}, de maniere a eviter l'erreur statistique qu'entraine la transformation de la distribution 2{pi} en distribution 4{pi}, et qui porteront sur differentes energies cinetiques prises comme parametres. (author) [Spanish] Los fragmentos resultantes de la fision del {sup 235}U por neutrones termicos se separan exactamente segun su masa y energia cinetica con ayuda de un espectrometro de masas en el microsegundo que sigue a la fision. Los fragmentos separados se recogen en una emulsion Ilford G-5 sensible a las particulas beta, colocada en el plano focal del espectrometro. El revelado de las emulsiones irradiadas se efectua, en lo posible, despues de haber transcurrido un tiempo suficientemente largo en relacion con el periodo mas prolongado que aparece en la cadena de desintegracion considerada. Los periodos del orden de dias o mas largos no se tienen en cuenta, pero pueden introducirse facilmente las correcciones adecuadas. Despues del revelado de la emulsion, pueden verse al microscopio todas las trazas de particulas beta que surgen del extremo de la traza de cada fragmento de fision. La posibilidad de correlacionar cada traza de particula beta con la traza de un fragmento de fision determinado permite calcular el numero n(x) de fragmentos de fision a los que corresponden x trazas de particulas beta, lo que indica no solo la longitud media de la cadena, sino tambien la distribucion de las particulas beta. Como el producto final

  3. Cross-Sections for Low-Energy Neutron-Induced Fission; Sections Efficaces de Fission pour des Neutrons de Faible Energie; 0421 0415 0427 0415 041d 0418 042f 0414 0415 041b 0415 041d 0418 042f , 0412 042b 0417 0412 0410 041d 041d 041e 0413 041e 041d 0415 0419 0422 0420 041e 041d 0410 041c 0418 041d 0418 0417 K 041e 0419 042d 041d 0415 0420 0413 0418 0418 ; Secciones Eficaces en la Fision Inducida por Neutrones de Baja Energia

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    Rae, E. R. [Atomic Energy Research Establishment, Harwell, Didcot, Berks. (United Kingdom)

    1965-07-15

    charge des noyaux cibles fournit egalement de nombreux renseignements sur la structure des noyaux lourds. Dans le cas d'un noyau cible susceptible de fission thermique, lorsque l'energie des neutrons augmente, la section efficace presente d'abord des variations inversement proportionnelles a la vitesse, puis une region ou des pics de resonance aigus apparaissent, et en dernier lieu une region de continu caracterisee par des variations relativement regulieres. Tous ces phenomenes peuvent recevoir une explication theorique, mais il semble tres difficile d'expliquer quantitativement certaines caracteristiques des donnees. Lors de mesures recentes de sections efficaces destinees a repondre aux besoins de la technologie des reacteurs, les chercheurs se sont surtout efforces d'ameliorer la resolution en energie ainsi que la precision des donnees relatives aux combustibles; ils ont ete ainsi amenes a etudier plus en detail la region de resonance qui a un grand interet pour les calculs de l'effet Doppler dans les reacteurs. Des mesures plus precises a des niveaux d'energie assez eleves ont fait apparaitre dans certains cas l'existence de sections efficaces de fission assez importantes en dessous du seuil d'energie de fission. Ces mesures ont ensuite appele l'attention des chercheurs sur l'interpretation des sections efficaces en fonction de modeles nucleaires qui reposent sur des donnees quantitatives sures. Le memoire expose les principales caracteristiques des sections efficaces de fission par neutrons et en donne une interpretation. Il met l'accent sur les ameliorations qui ont recemment ete apportees a la qualite des mesures et aux essais d'interpretation quantitative de certains aspects des donnees recueillies. (author) [Spanish] Las secciones eficaces de fision, inducida por neutrones, de los nucleos pesados son de fundamental importancia para la tecnologia de la produccion de energia nuclear. Asimismo, la manera en que estas secciones eficaces varian segun la energia

  4. 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

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

    1962-03-15

    reactions provoquees par des neutrons rapides, en insistant sur les conditions que doivent remplir, dans les reacteurs, les donnees nucleaires fondamentales. (author) [Spanish] El autor examina el estado actual de los conocimientos acerca de las reacciones inducidas por los neutrones rapidos que se utilizan en el proyecto de reactores nucleares. Estudia con particular atencion los metodos experimentales microscopicos, sus resultados y la precision de los mismos. Considera con detalle la dispersion de los neutrones rapidos, y da los resultados de mediciones experimentales de la dispersion en el caso del oxigeno, hierro, zirconio, niobio, wolframio, torio y uranio. Expone los resultados mas significativos de los estudios experimentales de la captura de neutrones rapidos y de la fision inducida por los mismos. Las mediciones estudiadas no solo conducen a resultados de gran utilidad practica, sino que sirven como ejemplos de la aplicacion de las tecnicas nucleares experimentales mas modernas. El autor indica los terrenos en que la informacion experimental es limitada, contradictoria o inexistente. Por ultimo, formula previsiones sobre el desarrollo de los conocimientos relativos a las reacciones de los neutrones rapidos, subrayando lo referente al cumplimiento de las condiciones necesarias para que el reactor proporcione datos nucleares basicos. (author) [Russian] V doklade rassmatrivaetsya primenenie shiroko rasprostranenny kh znanij o reaktsiyakh, vyzyvaemykh bystrymi nejtronami v yadernykh proektakh reaktornykh sistem. Osnovnoe znachenie pridaetsya mikroskopicheski m ehksperimental'ny m metodam, rezul'tatam i tochnosti. Podrobno rassmatrivaetsya rasseyanie bystrykh nejtronov, vklyuchaya rezul'taty ehksperimental'nogo opredeleniya rasseyaniya na kislorode, zheleze, tsirkonii, niobii, vol'frame, torii i urane. Privodyatsya dannye, poluchennye v rezul'tate ehksperimental'ny kh issledovanij zakhvata bystrykh nejtronov i deleniya, vyzvannogo nejtronami. Izmereniya, privedennye v

  5. Pathogenesis of Intrapulmonary Haemorrhage in Dogs Exposed to Pulsed Fission-Spectrum Neutrons; Pathogenese de l'Hemorragie Intrapulmonaire chez des Chiens Exposes a des Neutrons de Fission Pulses; Patogenez vnutrilegochnykh krovoizliyanij u sobak pri obluchenii impul'snymi nejtronami spektra deleniya; Patogenesis de la Hemorragia Intrapulmonar en Perros Expuestos a Neutrones de Fision Pulsados

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    Jones, R. K.; Engel, R. E.; Godden, W. R. [Kirtland AFB, New Mexico (United States)

    1964-05-15

    atteints presentaient un gonflement endothelial extremement marque, mais leur tunique moyenne ne presentait pas de modifications essentielles. On notait egalement une hemorragie peribronchiale au niveau des arteres pulmonaires atteintes. La pathogenese de ces alterations semble etre liee primitivement a une deterioration de l 'endothelium provoquee par les neutrons de fission puises; un facteur complementaire est vraisemblablement la thrombocytopenie, puisqu'on a constate que le nombre de megacaryocytes de la moelle etait inversement proportionnel a'la gravite de l'hemorragie intiapulmonaire. (author) [Spanish] La comparacion de las alteraciones de los tejidos en perros expuestos a rayos X de 250 kVp y a un haz pulsado de neutrones de fision, efectuada anteriormente en el mismo laboratorio, revelo que las reacciones son similares en lineas generales. Sin embargo, los pulmones de los animales expuestos a neutrones de fision son mucho mas propensos a las hemorragias peribronquiales y perivasculares. Los autores han intentado definir la patogenesis de esta lesion exponiendo 5 sabuesos a una dosis de 400 rad (dosis maxima admisible) de un haz de neutrones rapidos procedentes de un reactor tipo GODIVA (sin reflector) y sacrificando luego los animales a intervalos regulares. Cinco dias despues de la irradiacion, se manifestaron serias alteraciones patologicas constituidas por pequenas hemorragias pulmonares esporadicas en la periferia. Hacia el noveno dia, el numero de estas hemorragias aumenta progresivamente. Los cambios mas notables ocurren a los 13 dias y consisten en extensas hemorragias perivasculares en torno a las ramas de la arteria pulmonar, desde el hilio hasta la superficie de la pleura. Las primeras modificaciones histologicas en los pulmones se observaron a los cinco dias: se trata de zonas focales bien delimitadas de congestion alveolar, acompanadas por una hinchazon de las celulas del endotelio capilar y una leve extravasacion alveolar de los hematies. Estos

  6. Saddle-Point Rotational States from Resonance Fission of Oriented Nuclei; Etats Rotationnels a l'Etranglement Resultant de la Fission, par Neutrons de Resonance, de Noyaux Orientes; 0412 0420 0410 0429 0410 0422 0415 041b 042c 041d 042b 0415 0421 041e 0421 0422 041e 042f 041d 0418 042f 0421 0415 0414 041b 041e 0412 041e 0419 0422 041e 0427 K 0418 0412 0420 0415 0417 0423 041b 042c 0422 0410 0422 0415 0420 0415 0417 041e 041d 0410 041d 0421 041d 041e 0413 041e 0414 0415 041b 0415 041d 0418 042f 041e 0420 0418 0415 041d 0422 0418 0420 041e 0412 0410 041d 041d 042b 0425 042f 0414 0415 0420 ; Estados Rotacionales en el Punto de Estrangulacion Debidos a la Fision por Resonancia de Nucleos Orientados

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    Dabbs, J. W.T.; Walter, F. J.; Parker, G. W. [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1965-07-15

    valeurs de J dans {sup 235}U, on a procede a un ajustement a of analogue a celui de Kirpichnikov et al., pour lequel il avait ete admis que J (0,3 eV) etait different de J (1,14 eV), contrairement a ce qui avait ete fait pour des ajustements a plusieurs niveaux anterieurs. Ces donnees preliminaires sont compatibles avec une anisotropie proportionnelle a la contribution a of des deux valeurs de J possibles, qui a ete calculee. Toutefois, la forme de la courbe n'est pas en accord avec d'autres donnees, telles que la variation du rapport 'sommet-vallee ' de Faler et Tromp; en consequence, bien qu'elle paraisse extremement plausible, l'hypothese Selon laquelle J (0,3 eV) est different de J (1,14 eV) ne doit pas encore etre consideree comme demontree. On procede actuellement a de nouvelles mesures. (author) [Spanish] Los nucleos de los elementos actinidos uranio, neptunio y plutonio pueden alinearse en los compuestos del tipo XO{sub 2}Rb(NO{sub 3}){sub 3}, en virtud de la interaccion del momento cuadripolar del nucleo con el gradiente del campo electrico cristalino, por simple enfriamiento del monocristal correspondiente. Una alineacion nuclear de este tipo corresponde a una distribucion angular no uniforme del eje de simetria del nucleo compuesto en el espacio, que refleja principalmente el valor de K. Si se supone que los fragmentos presentan tambien la misma distribucion, se obtiene un metodo para determinar el numero cuantico K en el punto de estrangulacion. Como se menciona en trabajos anteriores, en el Oak Ridge National Laboratory se han realizado experimentos con nucleos alineados de {sup 233}U y de {sup 235}U a 1,2 Degree-Sign K utilizando neutrones termicos. Dichos experimentos se han ampliado ahora a energias neutronicas de resonancia y a temperaturas de 0, 5 Degree-Sign K. Si se considera juntamente con la determinacion directa (mediante neutrones y nucleos polarizados) de los valores J asociados a cada resonancia, esa ampliacion permite llegar a un conocimiento

  7. Delayed Neutrons and Photoneutrons from Fission Products; Neutrons Retardes et Photoneutrons Emis par des Produits de Fission; 0417 0410 041f 0410 0417 0414 042b 0412 0410 042e 0429 0418 0415 041d 0415 0419 0422 0420 041e 041d 042b 0418 0424 041e 0422 041e 041d 0415 0419 0422 0420 041e 041d 042b 041f 0420 041e 0414 0423 041a 0422 041e 0412 0414 0415 041b 0415 041d 0418 042f ; Neutrones Retardados y Fotoneutrones de los Productos de Fision

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    Amiel, S. [Soreq Nuclear Research Centre, Atomic Energy Commission, Yavne (Israel)

    1965-07-15

    . Chacun de ces groupes correspond a un ensemble complexe de nucleides. Il est important de disposer de donnees detaillees sur les constituants de ces groupes pour les reacteurs dans lesquels il peut se produire un fractionnement de la fission qui peut modifier les abondances relatives des groupes. Ces donnees n'existent que pour les produits de fission a longue periode dont les proprietes et les rendements sont bien connus; les resultats experimentaux concordent avec les valeurs obtenues a partir des distributions selon la masse et la charge et des schemas de desintegration. L'identification des differents nucleides appartenant aux groupes a courte periode, plus complexes, presente des difficultes considerables, mais etant donne l'importance de ces donnees du point de vue tant pratique que theorique, il serait justifie de poursuivre de Inverted-Question-Mark etudes approfondies a ce sujet,. (author) [Spanish] Neutrones retardados: La mayoria de los estudios realizados sobre los neutrones retardados emitidos en el proceso de-fision han entranado el analisis cfei comportamiento cinetico de los sistemas de fisiones en cadena, el analisis de la desintegracion neutronica total (resuelta en 6 grupos con periodos del orden de 0,2, 0,5, 2, 6, 22 y 55 s) , y algunas mediciones de ios espectros neutronicos (extendiendose la gama de energias de 0,1 a 1,2 MeV. con el valor maximo en el intervalo de 0,2-0, 5 MeV). La separacion rapida de los halogenos producidos por fision ha senalado a 7 isotopos ({sup 87,88,89,90}Br et {sup 137,138,139}I) como precursores de neutrones retardados, y el analisis de los gases nobles ha permitido determinar otros das, a saber, el Kr con periodo de 1.5 s, y el Rb de 6 s. A estos precursores identificados, corresponde el 80% aproximadamente de los rendimientos totales de neutrones retardados. Las predicciones teoricas de los posibles precursores senalan que en las regiones que siguen inmediatamente a las capas neutronicas completas han de encontrarse unas

  8. In Vivo and Air Dosimetry of Fission-Spectrum Neutrons; Dosimetrie In Vivo et dans l'Air du Spectre des Neutrons de Fission; Dozimetriya v vozdukhe i dozimetriya In Vivo nejtronov spektra deleniya; Dosimetria In Vivo y en el Aire de Neutrones de un Espectro de Fision

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    Mobley, T. S.; Engel, R. E.; Godden, W. R. [Kirtland Airforce Base, New Mexico (United States); Penikas, V. T. [AFIT, Wright-Patterson Air Force Base, Ohio, with Duty Station at University of Rochester, School of Medicine and Dentistry, Rochester, NY (United States)

    1964-03-15

    laterales a une distance mediane de 200 cm ou de 175 cm du centre de l ' assemblage critique. La dose de neutrons mesuree dans l ' air etait de 161 {+-} 5 ,5 rad a 200 cm et de 242 {+-} 16.6 rad a 175 cm. A ces distances, la dose gamma etait respectivement de 33 {+-} 2,4 et 42 {+-} 2,5 r. Les doses d'entree et de sortie ainsi que la dose a l ' insertion variaient selon l'elevation de temperature due aux bouffees de neutrons, la distance du reacteur, l 'orientation des feuilles par rapport au reacteur et l'epaisseur et la composition de tissus attenuants. (author) [Spanish] Con el proposito de evaluar la configuracion de la dosis profunda durante la exposicion a neutrones de un espectro de fisionalos autores han ideado un metodo de dosimetria neutronica in vivo que aplicaron a ovejas. Utilizaron para estos estudios un reactor pulsante analogo al GODIVA II del Laboratorio Cientifico de Los Alamos. Dicho conjunto funciona de forma de producir impulsos de 50 {mu}s de amplitud, medida a la mitad de la altura maxima, y un ascenso de temperatura del combustible de unos 100 Degree-Sign C. Ademas, prepararon 'apositos ' subcutaneos que contienen una lamina de oro recubierta de cadmio, una lamina de oro sin recubrir y tres dosimetros de varilla de vidrio, termoluminiscentes, en un recipiente de plomo al litio revestido de vidrio. Estos apositos se introdujeron en el tejido subcutaneo, a ambos lados del cuerpo, y sirvieron para medir el flujo integrado de neutrones termicos y la dosis gamma, a medida que la irradiacion neutronica se aplica 'lateralmente'. Los apositos abdominales se prepararon en forma semejante a los subcutaneos; constan de una esfera de boro que contiene laminas de umbral de fision (Pu, Np, U) recubiertas de cadmio, una pastilla de azufre y los mismos tres tipos de dosimetros que forman parte del aposito subcutaneo. El aposito dosimetrico se sujeto al pilar anterior del rumen del animal 18 h antes de someterlo a la exposicion. En la memoria se describe la tecnica de

  9. Synovectomy by Neutron capture; Sinovectomia por captura de neutrones

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    Vega C, H.R.; Torres M, C. [Centro Regional de Estudios Nucleares, Universidad Autonoma de Zacatecas, C. Cipres 10, Fracc. La Penuela, 98000 Zacatecas (Mexico)

    1998-12-31

    The Synovectomy by Neutron capture has as purpose the treatment of the rheumatoid arthritis, illness which at present does not have a definitive curing. This therapy requires a neutron source for irradiating the articulation affected. The energy spectra and the intensity of these neutrons are fundamental since these neutrons induce nuclear reactions of capture with Boron-10 inside the articulation and the freely energy of these reactions is transferred at the productive tissue of synovial liquid, annihilating it. In this work it is presented the neutron spectra results obtained with moderator packings of spherical geometry which contains in its center a Pu{sup 239} Be source. The calculations were realized through Monte Carlo method. The moderators assayed were light water, heavy water base and the both combination of them. The spectra obtained, the average energy, the neutron total number by neutron emitted by source, the thermal neutron percentage and the dose equivalent allow us to suggest that the moderator packing more adequate is what has a light water thickness 0.5 cm (radius 2 cm) and 24.5 cm heavy water (radius 26.5 cm). (Author)

  10. Neutron induced electron radiography; Radiografia com eletrons induzida por neutrons

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    Andrade, Marcos Leandro Garcia

    2008-07-01

    In the present paper a new radiography technique, the 'Neutron Induced Electron Radiography' - NIER, to inspect low thickness samples on the order of micra, has been developed. This technique makes use of low energy electrons as penetrating radiation generated from metallic gadolinium screens when irradiated by thermal neutrons. The conditions to obtain the best image for the conventional X-ray film Kodak-AA were determined by using a digital system to quantify the darkening level of the film. The irradiations have been performed at a radiography equipment installed at the beam-hole no. 8 of the 5 MW IEA-R1 nuclear research reactor of IPEN-CNEN/SP. The irradiation time to obtain the best radiography was 100 seconds and for such condition the technique was able to discern 1 {mu}m in 24 {mu}m of aluminum at a resolution of 32 {mu}m. By visual comparison the images obtained by the NIER shown a higher quality when compared with the ones from other usual techniques the make use of electrons a penetrating radiation and films for image registration. Furthermore the use of the digital system has provided a smaller time for data acquisition and data analysis as well as an improvement in the image visualization. (author)

  11. 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

    exercee sur la gaine, il a utilise trois modeles ou le gaz etait contenu dans des interstices relies entre eux, dans des interstices separes ou dans un orifice central. Le memoire traite de la variation de la pression en fonction du volume libre (densite du combustible) et de la temperature. Des gaines en materiaux tres resistants, comme l'Inconel-X et le molybdene, ont pu supporter la pression des gaz de fission aux temperatures de fonctionnement . Malheureusement, les sections efficaces d'absorption de ces materiaux sont plus elevees que celle de l'aluminium. Les resultats de calculs multigroupes sont presentes, pour montrer comment ces materiaux de gainage et la diminution de la densite du combustible influent sur la masse critique et le rapport de surgeneration dans les reacteurs surgenerateurs de petites ou moyennes dimensions. (author) [Spanish] El costo del ciclo de combustible y el periodo de duplicacion en los reactores reproductores de neutrones rapidos dependen en gran medida del grado de combustion que pueda alcanzarse. La utilizacion de combustible en forma de oxido o de carburo permite obtener un grado de combustion de 100 000 MWd/t. Cuando se emplean elementos combustibles con revestimiento, el aumento de presion de los gases de fision constituye un factor limitativo. En el caso del elevado grado de combustion previsto, una fraccion considerable de los gases de fision penetra en los peros del material, contribuyendo asi a aumentar la presion en el interior de la envoltura. Sobre la base de los rendimientos de fision y de las cadenas de desintegracion conocidas, el autor ha evaluado la produccion de gas y el aumento de presion. Para calcular la presion ejercida sobre la envoltura, ha empleado tres modelos fisicos en que el gas estaba contenido en poros conectados entre si, en poros separados, o en un orificio central. El autor analiza la variacion de la presion, en funcion del volumen libre (densidad del combustible) y de la temperatura. Las envolturas de

  12. Mass and Charge Distribution in Low-Energy Fission; Repartition des Masses et des Charges dans la Fission a Basse energie; 0420 0410 0421 041f 0420 0415 0414 0415 041b 0415 041d 0418 0415 041c 0410 0421 0421 042b 0418 0417 0410 0420 042f 0414 0410 041f 0420 0418 0414 0415 041b 0415 041d 0418 0418 , 0412 042b 0417 0412 0410 041d 041d 041e 041c 0427 0410 0421 0422 0418 0426 0410 041c 0418 041c 0410 041b 041e 0419 042d 041d 0415 0420 0413 0418 0418 ; Distribucion de Masas y de Cargas en la Fision a Bajas Energias

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    Wahl, A. C. [Washington University, St. Louis, MO (United States)

    1965-07-15

    que la fission de {sup 235}U par neutrons thermiques - qui sont etudies comprennent la fission de {sup 233}U et de {sup 239} Pu par neutrons thermiques, la fission spontanee de {sup 240}Pu et de {sup 252}Cf, la fission de {sup 235} U et de {sup 238}U par des neutrons de 14 MeV, la fission de {sup 226}Ra par des protons de 1 MeV, et la fission de {sup 209}Bi par des deuterons de 22 MeV. (author) [Spanish] El autor examina con bastante detalle la distribucion de las masas y de las cargas en la fision del {sup 235}U inducida por neutrones termicos, comparandola seguidamente con las distribuciones observadas en otros procesos de fision a bajas energias. Entre las cuestiones que estudia en relacion con la distribucion de las masas en la fision binaria, figura la posicion de los picos y del valle, asi como la estructura fina en una curva de rendimiento masico respecto de las capas nucleares completas y los desplazamientos que se producen al cambiar el nucleo que se'fisiona y la energia de excitacion. Tambien estudia la distribucion de las masas en la fision ternaria. Tanto en el caso de la fision binaria como en el de la fision ternaria, formula observaciones acerca de la distribucion masica de los fragmentos primarios emitidos (antes de la evaporacion de neutrones) y de los productos de fision (emitidos despues de esa evaporacion). Examina la distribucion de las cargas atendiendo a la dispersion de estas entre los productos de fision de igual numero de masa, y a la variacion, en funcion de este numero de masa, de Zp, esto es, la ''carga mas probable'' (valor no entero) para un numero de masa dado. Aunque la informacion directa acerca de la distribucion de las cargas se limita a los productos de fision, el autor evalua tambien la distribucion de las cargas para los fragmentos de fision primarios. Los datos conocidos y los calculados, relativos a la distribucion de las masas y de las cargas en un proceso de fision, permiten calcular el rendimiento de todos los productos o

  13. Release of Fission Products from UC-ZrC Fuel Inserts; Degagement des produits de fission liberes dans des noyaux combustibles UC-ZrC; Vydelenie produktov deleniya iz topliv UC - ZrC; Liberacion de productos de fision por pastillas de combustible de UC-ZrC

    Energy Technology Data Exchange (ETDEWEB)

    Barth, F.; Von der Decken, C. B.; Schifferstein, K. [Brown Boveri/Krupp Reaktorbau G.M.B.H., Duesseldorf (Germany); Clauss, A.; Reichel, H.; Rygaert, J.; Ruston, W. R. [Societe d' Etudes de Recherches et d' Applications pour l' Industrie (S.E.R.A.I.), Brussels (Belgium)

    1963-11-15

    The release of fission products from pellets of the approximate composition UC + 20 ZrC has been investigated in a loop during irradiation. The purpose was to check the possibility to use these pellets as inserts for the spherical fuel elements of the high temperature reactor presently being built at Juelich by Brown-Boveri/Krupp Reaktorbau G.m.b.H. The tests were carried out on free pellets and on pellets enclosed in graphite capsules. Some pellets had a 1- to 2-mm thick border zone consisting of pure zirconium carbide. The samples were placed in electric resistance furnaces reaching a maximum temperature of 1600{sup o}C. The neutron fluxes during the irradiation were 3 to 4 x 10{sup 10} n/cm{sup 2}s. The loop permitted the measurement of the release of the rare gas isotopes Kr{sup 85m}, Kr{sup 87}, Kr{sup 88}, Xe{sup 133} and Xe{sup 135} during irradiation and the indirect determination of I{sup 133} and I{sup 135} after shut-down of the reactor. The minimum release of I{sup 131}, Sr{sup 89}, Ba{sup 140} and Ce{sup 141} was radiochemically determined after withdrawal of the specimen. It was also possible to measure the recoil fraction {epsilon}{sub R} alone when the fuel insert was suspended within a furnace of larger diameter. The measured values of {epsilon}{sub R} were only slightly higher than the calculated ones. At higher sample temperatures the diffusion fraction {epsilon}{sub D} could be calculated by subtraction of the recoil fraction from the total release. From {epsilon}{sub D} it was possible to calculate D/r{sub 0}{sup 2}s{sup -1} using the approximation equations of Fliigge and Zimens where D = diffusion constant and r{sub 0} = mathematically defined mean particle radius. The logarithmic plot of these values against 1/T yielded the activation energies (T = sample temperature in {sup o}K). The activation energies for the diffusion of krypton and xenon did not show significant differences. There were likewise no big differences in the activation

  14. Neutron spectrum for neutron capture therapy in boron; Espectro de neutrones para terapia por captura de neutrones en boro

    Energy Technology Data Exchange (ETDEWEB)

    Medina C, D.; Soto B, T. G. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Programa de Doctorado en Ciencias Basicas, 98068 Zacatecas, Zac. (Mexico); Baltazar R, A. [Universidad Autonoma de Zacatecas, Unidad Academica de Ingenieria Electrica, Programa de Doctorado en Ingenieria y Tecnologia Aplicada, 98068 Zacatecas, Zac. (Mexico); Vega C, H. R., E-mail: dmedina_c@hotmail.com [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas, Zac. (Mexico)

    2016-10-15

    Glioblastoma multiforme is the most common and aggressive of brain tumors and is difficult to treat by surgery, chemotherapy or conventional radiation therapy. One treatment alternative is the Neutron Capture Therapy in Boron, which requires a beam modulated in neutron energy and a drug with {sup 10}B able to be fixed in the tumor. When the patients head is exposed to the neutron beam, they are captured by the {sup 10}B and produce a nucleus of {sup 7}Li and an alpha particle whose energy is deposited in the cancer cells causing it to be destroyed without damaging the normal tissue. One of the problems associated with this therapy is to have an epithermal neutrons flux of the order of 10{sup 9} n/cm{sup 2}-sec, whereby irradiation channels of a nuclear research reactor are used. In this work using Monte Carlo methods, the neutron spectra obtained in the radial irradiation channel of the TRIGA Mark III reactor are calculated when inserting filters whose position and thickness have been modified. From the arrangements studied, we found that the Fe-Cd-Al-Cd polyethylene filter yielded a ratio between thermal and epithermal neutron fluxes of 0.006 that exceeded the recommended value (<0.05), and the dose due to the capture gamma rays is lower than the dose obtained with the other arrangements studied. (Author)

  15. Scattering of Neutrons by Liquid Bromine; Diffusion des neutrons par le brome liquide; R; Dispersion de neutrones por bromo liquido

    Energy Technology Data Exchange (ETDEWEB)

    Coote, G E; Haywood, B C [Atomic Energy of Canada Ltd., Chalk River, Ontario (Canada)

    1963-01-15

    energetica de los neutrones dispersos fue medida para angulos comprendidos entre 10{sup o} y 160{sup o}, mediante el metodo del tiempo de vuelo. La distribucion angular cbnfirma los resultados obtenidos en un estudio anterior por Caglioti. Los espectros fueron expresados en la forma correspondiente a la ''ley de dispersion'' S({alpha},{beta}) de Egelstaff y analizados para derivar la distribucion generalizada de frecuencias p({beta}) de los movimientos atomicos en el liquido. La funcion p({beta}) tiene un pico poco pronunciado, cuyo maximo corresponde a {beta}{approx}0,3 y no parece presentar saltos en el intervalo 0 < {beta} < 0,8 medido; la forma general de la curva confirma la descripcion del liquido como ''cuasi-cristalino''. Los autores examinan las dificultades que presenta la normalizacion absoluta de la funcion p({beta}). (author)

  16. Synovectomy by neutron capture in boron; Sinovectomia por captura de neutrones en boro

    Energy Technology Data Exchange (ETDEWEB)

    Vega C, H.R. [Unidades Academicas de Estudios Nucleares, Ingenieria Electrica y Matematicas, Universidad Autonoma de Zacatecas, A.P. 336, C.P. 98000 Zacatecas (Mexico)

    2002-07-01

    The rheumatoid arthritis is an illness which affect approximately at 3% of the World population. This illness is characterized by the inflammation of the joints which reduces the quality of life and the productivity of the patients. Since, it is an autoimmune illness, the inflammation is due to the overproduction of synovial liquid by the increase in the quantity of synoviocytes. The rheumatoid arthritis does not have a definitive recovery and the patients have three options of treatment: the use of drugs, the surgery and the radio synovectomy. The synovectomy by neutron capture in Boron is a novel proposal of treatment of the rheumatoid arthritis that consists in using a charged compound with Boron 10 that is preferently incorporated in the synoviocytes and to a less extent in the rest of surrounding tissues of the joint. Then, the joint is exposed to a thermal neutron field that induces the reaction (n, {alpha}) in the {sup 10} B. the products of this reaction place their energy inside synoviocytes producing their reduction and therefore the reduction of the joint inflammation. Since it is a novel procedure, the synovectomy by neutron capture in boron has two problems: the source design and the design of the adequate drug. In this work it has been realized a Monte Carlo study with the purpose to design a moderating medium that with a {sup 239} Pu Be source in its center, produces a thermal neutron field. With the produced neutron spectra, the neutrons spectra and neutron doses were calculated in different sites inside a model of knee joint. In Monte Carlo studies it is necessary to know the elemental composition of all the joint components, for the case of synovia and the synovial liquid this information does not exist in such way that it is supposed that its composition is equal than the water. In this work also it has been calculated the kerma factors by neutrons of synovia and the synovial liquid supposing that their elemental composition are similar to the

  17. Study of U{sup 235} neutron fission spectrum by the knowledge of cross sections average over that spectrum; Estudio del espectro de neutrones de fision del {sup 235}U a traves del conocimiento de secciones eficaces promediadas sobre dicho espectro

    Energy Technology Data Exchange (ETDEWEB)

    Suarez, P M [Comision Nacional de Energia Atomica, San Carlos de Bariloche (Argentina). Centro Atomico Bariloche

    1998-12-31

    A literature search of cross sections averaged over the fission neutron spectrum confirms inconsistencies between calculated and experimental values for high threshold reactions. Since, in this case, calculated averaged cross sections are systematically lower than measured values, it is concluded that the representations used to carry out these calculations underestimate the number of neutrons in the high energy region of the spectrum. A careful measurement of the averaged cross section for the {sup 45}Sc(n,2n) {sup 44g}Sc and {sup 45}Sc(n,2n) {sup 44m}Sc high threshold reactions had been performed in the RA-6 Neutron Activation Analysis Laboratory after carefully checking that the neutron flux at the core position where the samples were being irradiated was indeed an undisturbed fission spectrum. The experimental values are greater than those calculated with either, Watt type representations or the one based on the Madland and Nix model for the prompt fission spectrum. In many areas of nuclear engineering, like validation of nuclear data, reactor calculations, applied nuclear physics, shielding design, etc., it is of great practical importance to have a representation for the neutron flux that can be expressed in a closed analytical form and that agrees with experimental results, specially for the most widely fissile nuclide, {sup 235}U. The results of the calculations mentioned above lead us to propose an analytical form for the {sup 235}U fission neutron spectrum that better agrees with experimental results in the whole energy spectrum. We propose two different forms; both are a modification of the Watt-type form that has been adopted within the ENDF/B-V files. One of the new analytical representations is defined in two regions: below 9.5 MeV it is exactly the same formula as that used within the ENDF/B-V files, above this energy the parameters of this formula are changed. The other proposed analytical representation is expressed by a single formula in the whole

  18. Activación del topacio natural irradiado por neutrones en el núcleo del reactor RP-10

    OpenAIRE

    Gómez, J.; Parreño, Fernando; Lázaro, Gerardo; Vela, Mariano

    2003-01-01

    Se obtuvieron cristales de topacio activados al ser irradiados con neutrones dentro del núcleo del reactor RP-10. La activación depende del flujo de neutrones, por ello se desarrolló portamuestras (canes de irradiación) para absorber que son los causantes de la activación

  19. Neutron-induced alpha radiography; Radiografia com particulas alfa induzida por neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Marco Antonio Stanojev

    2008-07-01

    A new radiography technique to inspect thin samples was developed. Low energy alpha particles, generated by a boron based screen under thermal neutron irradiation, are used as penetrating radiation. The solid state nuclear track detector CR-39 has been used to register the image. The interaction of the {alpha} - particles with the CR-39 gives rise to damages which under an adequate chemical etching became tracks the basic units forming the image. A digital system was developed for data acquisition and data analysis as well as for image processing. The irradiation and etching conditions to obtain the best radiography are 1,3 hours and 25 minutes at 70 deg C respectively. For such conditions samples having 10 {mu}m in thickness can be inspected with a spatial resolution of 32 {mu}m. The use of the digital system has reduced the time spent for data acquisition and data analysis and has improved the radiography image visualization. Furthermore, by using the digital system, it was possible to study several new parameters regarding the tracks which are very important to understand and study the image formation theory in solid state nuclear track detectors, the one used in this thesis. Some radiography images are also shown which demonstrate the potential of the proposed radiography technique. When compared with the other radiography techniques already in use to inspect thin samples, the present one developed in the present paper allows a smaller time to obtain the image, it is not necessary to handle liquid radioactive substances, the detector is insensitive to {beta}, {gamma}, X-ray and visible light. (author)

  20. The Determination of Uranium in Urine by Delayed Neutron Counting; Dosage de l'Uranium dans l'Urine par Comptage des Neutrons Differes; Opredelenie soderzhaniya urana v moche putem scheta zapazdyvayushchikh nejtronov; Determinacion del Uranio Contenido en la Orina por Recuento de Neutrones Retardados

    Energy Technology Data Exchange (ETDEWEB)

    Brookes, I. R. [Atomic Weapons Research Establishment, Aldermaston, Berks. (United Kingdom)

    1965-10-15

    polyethylene d'une capacite de 2,85 cl, qui est scelle a chaud. Le flacon contenant l'echantillon est enferme dans un tube et envoye par un systeme pneumatique dans le coeur du reacteur HERALD ou il est irradie par un fieux de neutrons thermiques de 3,94 * 10{sup 12}n/cm{sup 2}s. Apres une irradiation de 1 min, l'echantillon retourne automatiquement au laboratoire ou le flacon contenant l'echantillon est place dans un compteur a neutrons. Ce compteur est mis en marche 25 s apres que l'echantillon a quitte le reacteur et compte l'echantillon pendant 1 min. Les echantillons temoins se composent d'urine provenant de personnes qui ne sont pas professionnellement exposees a l'uranium; l'etalon est une quantite connue de {sup 235}U (sous forme d'uranium naturel). La limite de detection est de 0,020 pCi d'uranium enrichi a 93% ou de 0,026 {mu}g d'uranium naturel (0,007 de la charge corporelle maximale admissible) et de 0,036 {mu}g d'uranium naturel pour 100 ml d'urine. Elle depend du nombre de coups correspondant aux temoins. La composante principale du temoin est la reponse du compteur aux rayons gamma emis par les produits d'activation que l'urine irradiee contient. Il faut 3,5 min environ pour irradier et compter un echantillon et l'on peut, au cours d'une journee de travail, faire evaporer et traiter 50 echantillons pour les mettre en flacons. Pour les analyses d'urine, l'influence de {sup 239}Pu peut etre consideree comme negligeable. (author) [Spanish] Con arreglo al metodo del autor, el uranio-235 se determina por recuento de los neutrones retardados emitidos a raiz de la fision por neutrones termicos del {sup 235}U contenido en la muestra. Los tres grupos de neutrones que se consideran tienen periodos de 55, 72, 22, 72 y 6, 22 s, respectivamente. En un bano Maria se evaporan a sequedad 100 mi de orina. El residuo se pasa con unos 4 a 5 mi de agua a un frasco de polietileno de 1 onza, que se cierra seguidamente por soldadura termica. El frasco con la muestra se coloca en un

  1. The Prompt Gamma-Ray, Prompt Electron and Prompt X-Ray Spectra Associated with Fission Fragments of Specific Mass; Spectres de Rayons Gamma Instantanes, d'Electrons Instantanes et de Rayons X Instantanes Associes a des Fragments de Fission de Masse Donnee; 041c 0413 041d 041e 0414 ; Espectros de Rayos Gamma. Electrones y Rayos X Inmediatos, Vinculados a Fragmentos de Fision de Masa Determinada

    Energy Technology Data Exchange (ETDEWEB)

    Bowman, H. R.; Thompson, S. G.; Watson, R. L.; Kapoor, S. S.; Rasmussen, J. O. [Lawrence Radiation Laboratory, University of California, Berkeley, CA (United States)

    1965-07-15

    detectores de semiconductores, de elevado poder de resolucion. Las masas de los fragmentos se dedujeron de sus respectivas energias y las cargas nucleares se determinaron midiendo las energias de los rayos X-K vinculadas a las distintas masas. La magnitud y el signo del desplazamiento de Doppler permitio asignar les lineas espectrales de ios rayos gamma, a cada uno de los componentes de cada par de fragmentos. El desplazamiento de Doppler permite tambien medir independientemente la velocidad de los fragmentos y, por consiguiente, la masa de estos despues de la emision de un neutron. Los resultados de las mediciones realizadas sobre los rayos X concuerdan con la hipotesis de que la mayoria de los rayos X inmediatos emitidos durante la fision espontanea del {sup 252}Cf, son resultado de la conversion interna en los fragmentos de la fision primaria,, durante la desexcitacion de estados colectivos de baja energia. Ademas de los resultados concretos examinados en U memoiia, la consecuencia mas importante de los experimentos descritos es la demostracion de que es posible estudiar por separado las propiedades de cada fragmento de fision, identificado por sus radiaciones caracteristicas (en lugar de estudiar las propiedades de un fragmento de fision medio, con masa y carga tambien medias). Se estudian actualmente las consecuencias de este adelanto logrado en la tecnica de estudio de los fragmentos de fision. (author) [Russian] Nabljudalis' horosho opredelennye mgnovennye gamma-kvanty, mgnovennye konversionnye jelektrony i rentgenovskoe K-izluchenie v sovpadenii s dvizhushhimisja oskolkami delenija kalifornija-252. V neskol'kih sluchajah byli ustanovleny massy i zarjady jader, ispuskajushhih gamma-kvanty i konversionnye jelektrony. Jenergii gamma-kvantov, mgnovennyh jelektronov i mgnovennyh rentgenovskih luchej, a takzhe jenergii dvuh oskolkov delenija byli izmereny s pomoshh'ju tverdogo schetchika s vysokoj razreshajushhej sposobnost'ju. Massy oskolkov byli vyvedeny na osnove ih

  2. Patterns of Lethality and Absorbed Dose Distributions in Mice for Monoenergetic Neutrons; Letalite et Distribution de la Dose Absorbee chez la Souris pour des Neutrons Monoenergetiques; Letal'nost' i raspredelenie pogloshchennoj dozy pri obluchenii myshej monoehnergeticheskimi neitronami; Letalidad y Distribucion de las Dosis Absorbidas por el Raton para Neutrones Monoenergeticos

    Energy Technology Data Exchange (ETDEWEB)

    Frigerio, N. A.; Jordan, D. L. [Argonne National Laboratory, Argonne, IL (United States)

    1964-03-15

    V {+-} 50 keV pour couvrir la region des resonances de N et de O. On a constate que la courbe de letalite est une fonction marquee de Tenergie des neutrons et une fonction egalement marquee mais independante de la distribution de la dose. Toutefois, quelles que soient la dose, l'energie et la distribution, tous les animaux qui ont survecu 5 j ont ensuite survecu au moins 144 j, puis sont morts sous les effets a long terme habituels. Cela donne a penser que les neutrons rapides monoenergetiques n ayant pas subi de contamination gamma ou epithermique produisent presque exclusivement la 'mort intestinale ' precoce. (author) [Spanish] La presencia de intensas resonancias para el C, el N y el O, en el intervalo de 100 a 1500keV, ha permitido estudiar las interacciones especificas neutron-nuclido, que se manifiestan por variaciones de la letalidad, maximos de la EBR, etc. Mediante protones resueltos de 62 {mu}A, procedentes de un acelerador de van de Graaf, de 1882 keV a 2738 keV, se obtuvieron neutrones monoenergeticos por intermedio de la reaccion {sup 7}Li(p, n){sup 7}Be. Los autores expusieron al efecto de los neutrones monoenergeticos a hembras de raton virgenes, CF-1, en capsulas de celuloide, a distancias de 3,1 a 11,3 cm de la fuente, bajo angulos de 0 a 1 radian. Durante la exposicion bilateral, los animales giraban simultaneamente en orbitas circulares o elipticas normales al eje del haz. De esta manera se podia regular la distribucion de la dosis en el cuerpo del animal. Los autores midieron el flujo absoluto con contadores de fision de {sup 235}U y por receuento absoluto mediante alambres y laminas de oro activados, revestidos de Gd. Determinaron las dosis absorbidas con microcamaras de ionizacion y con un dosimetro de FeSO{sub 4}-NH{sub 4}SCN de alta sensibilidad, preparado especialmente para este fin. Para la medicion de las dosis relativas, usaron contadores gaseosos de Hurst para protones de retroceso y centelleadores de {sup 10}B, {sup 6}Li y de protones de

  3. Diagnosis of mucoviscidosis by neutron activation analysis. Part 1; Diagnostico da mucoviscidose utilizando analise por ativacao com neutrons. Parte 1

    Energy Technology Data Exchange (ETDEWEB)

    Bellido, Luis F.; Bellido, Alfredo V

    1997-02-01

    Symptoms pathology, incidence, and gravity of the inherent syndrome called mucoviscidosis, or cystic fibrosis are described in this Part I. The analytical methods used for its diagnosis, both the conventional chemical ones and by neutron activation analysis are also summarised. Finally, an analytical method to study the incidence of mucoviscidosis in Brazil is presented. This , essentially, consists in bromine determination, in fingernails, by resonance neutron activation analysis. (author) 33 refs., 13 figs.

  4. Essential and toxic element determination in edible mushrooms by neutron activation analysis; Determinacao de elementos essenciais e toxicos em cogumelos comestiveis por analise por ativacao com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Moura, Patricia Landim da Costa

    2008-07-01

    In this study concentrations of As, Br, Co, Cr, Cs, Fe, K, Na, Rb, Se and Zn were determined in edible mushrooms acquired from commercial establishments in the city of Sao Paulo and directly from Mogi das Cruzes, Suzano, Juquitiba and Mirandopolis producers. The analytical technique used for determining these elements in edible mushrooms was Instrumental Neutron Activation Analysis (INAA). Species of the Agaricus, Lentinus and Pleurotus genera were acquired during the period from November, 2006 to March, 2007. About 150 to 200 mg of freeze-dried mushrooms were irradiated in a neutron flux of 1012 cm{sup -2} s{sup -1} for 8 hours in the IEA-R1 nuclear research reactor at IPEN-CNEN-SP. In order to evaluate the precision and accuracy of the methodology, four reference materials: INCT-MPH-2 Mixed Polish Herbs and INCT-TL-1 Tea Leaves, NIST SRM 1577b Bovine Liver, and the material Mushroom from IAEA were analyzed. Results showed some variation in the element concentrations among the different genera. In some samples, arsenic was found but in low concentrations. Arsenic is probably derived from the contamination from pesticides used in the cultivation, in their the substrates where mushrooms uptake their nutrients. Although there are element concentration variations, mushrooms can still be considered a very rich nutritional source, mainly because of their low concentrations of Na, and due to the good source of K, Fe and Zn. (author)

  5. Determination os essential elements in diet and light foods using neutron activation analysis; Determinacao de elementos essenciais em alimentos diet e light por analise por ativacao com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Ito, Gerson Hideo [Universidade de Sao Paulo (USP), SP (Brazil). Inst. de Quimica]. E-mail: gehideo@gmail.com; Maihara, Vera Akiko [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Lab. de Analise por Ativacao Neutronica]. E-mail: vmaihara@ipen.br

    2007-07-01

    The object of this study was to determine essential elements on the diet and light foods and their normal similar through the neutron activation analysis (NAA) and to compare their results. Samples of sweetning, cappuccino, gelatine and chocolate collected at the Sao Paulo commerce were irradiated by a period of 8 hours, under a 10{sup 12} n cm{sub -2} s{sub -1} thermal neutron flux at the IEA-R1 research reactor - IPEN/CNEN-SP, Brazil, together with reference materials and elementary standards, for the determination the concentrations of Br, Ca, Cr, Co, K, Na, Fe, Se and Zn. The obtained results shown that the diet gelatine samples presented concentrations higher for determined elements related to the light and normal gelatines samples. Compared with cappucino samples there was not differences among the concentrations of the determined elements, excepted the element Cr for the cappuccino light. For the chocolate light they presents higher values related to the normal type. The sweetening did not present differences among the samples. (author)

  6. Neutronic density perturbation by probes; Pertubacion de densidades neutronicas por sondas

    Energy Technology Data Exchange (ETDEWEB)

    Vigon, M A; Diez, L

    1956-07-01

    The introduction of absorbent materials of neutrons in diffuser media, produces local disturbances of neutronic density. The disturbance depends especially on the nature and size of the absorbent. Approximated equations which relates te disturbance and the distance to the absorbent in the case of thin disks have been drawn. The experimental comprobation has been carried out in two especial cases. In both cases the experimental results are in agreement with the calculated values from these equations. (Author)

  7. Determination of essential trace elements in wine by neutron activation analysis; Determinacao de elementos essenciais em vinhos por analise por ativacao com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Daniele, Anna Paula

    2016-07-01

    Several studies have been carried out for determining essential elements in foodstuffs, including wine, due to its important nutritional role in human body functions. It was shown that daily consumption of wine in moderation contributes significantly to the needs of essential elements in human body such as Ca, Co, Cr, Fe, K, Mg, Mn, Zn, V, among others, and has health benefits in the prevention of numerous diseases and longer life expectancy, related in particular to the intake of antioxidants such as polyphenolic compounds. Trace elements are good indicators of origin of wines and their concentrations can be used as criteria to ensure authenticity, quality and show that the tolerance limits established by law were respected throughout the production process. However, although Brazilian wine industry is among the 15 largest in the world, analytical studies for organic and inorganic compounds of wine content are still small when compared to other major producers. In this sense, this study aimed to evaluate some procedures of wine sample preparation to determine essential elements by Instrumental Neutron Activation Analysis (INAA) and compare the results with those determined by Inductively Coupled Plasma Atomic Emission Spectrometry (ICP OES). Three sample preparation procedures were studied: freeze-drying, evaporation and dry ashing. The parameters studied were precision, accuracy and detection limit. ANOVA and Tukey-Kramer tests were applied to verify the statistical differences between the mean values obtained by the three wine preparation procedures for INAA with those means obtained by ICP OES. It was noticed that about 60% of results obtained by freeze-drying agreed with those obtained by ICP OES. (author)

  8. Neutron activation analysis of phytotherapic obtained from medicinal plants; Analise por ativacao com neutrons de fitoterapicos obtidos de plantas medicinais

    Energy Technology Data Exchange (ETDEWEB)

    Moreira, Henrique S. [Universidade de Sao Paulo (USP), Ribeirao Preto, SP (Brazil). Faculdade de Ciencias Farmaceuticas]. E-mail: hs_moreira@hotmail.com; Saiki, Mitiko; Vasconcellos, Marina B.A. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)]. E-mails: mitiko@ipen.br; mbvascon@ipen.br

    2007-07-01

    This paper determines the inorganic constituents in phytotherapic samples for posterior study of the relationship existent among the concentrations of the found elements and the their possible therapeutical effects. The samples of phytotherapic pills (Centella asiatica, Ginkgo biloba and Ginseng) were analysed by using neutron activation analysis (NAA). The As, Br, Ca, Co, Cr, Cs, Fe, K, La, Na, Rb, Sc, Se and Zn samples were determined in the phytotherapics, The Centella asiatica presented the higher concentrations of Br, Co, Cr, Fe, K, La, Na, Rb, Sc, Se and Zn. In the sample of Ginko biloba, higher levels of As and Ca were found, while in the sample ol Ginseng the element As were not detected. The found results have shown the the NAA method is appropriated for analysing this type of materials due to his simplicity, multielemental capacity and quality of the results obtained. (author)

  9. Short-Lived Antimony and Arsenic Isotopes Formed in Fission; Radioantimoine et Radioarsenic a Courte Periode Produits par la Fission; 041a 041e 0420 041e 0422 041a 041e 0416 0418 0412 0423 0429 0418 0415 0418 0417 041e 0422 041e 041f 042b 0421 0423 0420 042c 041c 042b 0418 041c 042b 0428 042c 042f 041a 0410 , 041e 0411 0420 0410 0417 041e 0412 0410 0412 0428 0418 0415 0421 042f 041f 0420 0418 0414 0415 - 041b 0415 041d 0418 0418 ; Isotopos de Periodo Corto del Antimonio y del Arsenico Formados por Fision

    Energy Technology Data Exchange (ETDEWEB)

    Tomlinson, L. [Atomic Energy Research Establishment, Harwell, Berks. (United Kingdom)

    1965-07-15

    The application of a new technique for the rapid separation of short-lived antimony and arsenic isotopes from fission products is described. The gamma spectra of Sb{sup 128}, Sb{sup 129} and Sb{sup 150} have been measured and previous observations con-firmed. A new delayed-neutron activity of 2-s half-life has been detected. The experimental data indicate that this activity is due to two isotopes, one of antimony and the other of arsenic. These are tentatively as-signed to Sb{sup 135} and one of the isotopes As{sup 85-87}. (author) [French] L'auteur expose Inapplication d'une methode nouvelle visant a separer rapidement le radioantimoine et le radioarsenic a courte periode des autres produits de fission. II a mesure les spectres gamma de {sup 128}Sb, {sup 129}Sb et {sup 130}Sb et obtenu confirmation d'observations precedentes. L'auteur a decele une nouvelle activite emettant des neutrons retardes et ayant une periode de 2 s. Selon des donnees ex peri mentales, cette activite est due a deux radioisotopes: un radioantimoine et un radioarsenic que l'auteur identifie provisoirement comme etant {sup 135}Sb et l'un des radioisotopes {sup 85-87}As. (author) [Spanish] El autor describe la aplicacion de una nueva tecnica para separar rapidamente los isotopos de periodo coito del antimonio y del arsenico de los productos de fision. Se han medido el espectro gamma del {sup 128}Sb, {sup 129}Sb y {sup 130}Sb y se han confirmado las observaciones anteriores. Se ha detectado una nueva actividad neurronica retardada cuyo periodo es de 2 s. Los resultados experimentales indican que esta actividad se debe a dos isotopos, uno del antimonio y otro del arsenico, que se suponen son el {sup 135}Sb, y uno de los isotopos {sup 85-87}As, respectivamente. (author) [Russian] Opisyvaetsja primenenie novogo metoda bystrogo otdelenija korotkozhivushih izotopov sur my i mysh'jaka ot produktov delenija. Provedeno izmerenie gamma-spektrov sur'my-128, 129 i 130, podtverzhdajutsja rezul

  10. The Scattering of Slow Neutrons from Hydrogen and Ethylene; Diffusion des neutrons lents par l'hydrogene et par l'ethylene; O rasseyanii medlennykh nejtronov vodorodom i ehtilenom; Dispersion de neutrones lentos por hidrogeno y etileno

    Energy Technology Data Exchange (ETDEWEB)

    Bally, D; Tarina, V; Todireanu, S [Institute of Atomic Physics, Bucharest (Romania)

    1963-01-15

    The angular distribution of 1.61 A wavelength neutrons scattered from hydrogen and ethylene has been measured. For ethylene the pressure was varied from 15 to 60 atm and for hydrogen from 60 to 110 atm. The investigated angular range was between 5''o and 90{sup o}. The experimental results obtained have been compared with the differential cross-section calculated using the Krieger-Nelkin formulae. (author) [French] Les auteurs ont mesure la distribution angulaire des neutrons ayant une longueur d'onde de 1,61 A diffuses par de l'hydrogene et par l'ethylene. Ils ont fait varier la pression de l'ethylene de 15 a 60 atm et celle de l'hydrogene de 60 a 110 atm. Le domaine angulaire etudie etait compris entre 5{sup o} et 90{sup o}. Les resultats des experiences ont ete compares aux sections efficaces differentielles calculees au moyen des formules de Krieger-Nelkin. (author) [Spanish] Los autores han medido la distribucion angular de neutrones de longitud de onda igual a 1,61 A, despersados por hidrogeno y etileno. En el caso del etileno, la presion vario de 15 a 60 atm y en el del higrogeno, de 60 a 110 atm. Los autores han explorado angulos comprendidos entre 5{sup o} y 90{sup o}. comparan los resultados experimentales obtenidos con el valor de la seccion eficaz diferencial calculado con ayuda de las formulas de Kriger-Nelkin. (author)

  11. Comparison of Clinical and Laboratory Responses in Sheep and Dogs following Whole-Body Exposures to 250-Kvp X-Rays and Fission-Spectrum Neutrons; Etude Comparee Clinique et en Laboratoire, des Reactions de Moutons et de Chiens a la Suite d'une Exposition du Corps Entier a des Rayons X de 250 Kv-Crete et a des Neutrons de Fission; Sravnenie klinicheskikh i laboratornykh dannykh o reaktsii ovets i sobak na obluchenie vsego tela rentgenovskimi luchami pri pikovom napryazhenii 250 Kv i nejtronami spektra deleniya; Estudio Comparado, Clinico y de Laboratorio, de las Reacciones de Ovejas y Perros Consecutivas a la Irradiacion del Cuerpo Entero con Rayos X de 250 KVp y Neutrones de Fision

    Energy Technology Data Exchange (ETDEWEB)

    Quaife, M. A.; Boer, J. de; Jones, R. K.; Ichiki, A. T.; Godden, W. R.; Davis, H.; Engel, R. E. [Kirtland AFB, New Mexico (United States)

    1964-05-15

    jour, la mortalite chez les chiens a ete de 50% pour les sujets exposes aux neutrons et de 93% pour les sujets exposes aux rayons X. Chez les moutons, les neutrons ont cause une mortalite de 22% et les rayons X une mortalite de 80%. (author) [Spanish] Los autores expusieron 15 ovejas y 8 perros a una dosis de 400 rad (en el aire) de un espectro pulsante de neutrones de fision y el mismo numero de ovejas y 14 perros a una dosis de 400 r (dosis media, en el aire) de rayos X de 250 kVp. Ademas, emplearon como testigos 7 ovejas y 4 perros sin irradiar. Efectuaron observaciones durante dos semanas, antes de proceder a la exposicion y, luego, a intervalos frecuentes y regulares una vez provocadas las lesiones. En las ovejas, la alteracion clinica mas sistematica fue la perdida total de la lana a los 51 dias de la exposicion. La piel subyacente presentaba un color rosado semejante a la leve erubescencia que se observa a veces en el hombre. Los perros no perdieron el pelo. El numero de polinucleares, neutrofilos, linfocitos y trombocitos disminuyo rapidamente despues de la irradiacion en ambas especies. Solamente en los grupos irradiados con neutrones, alrededor de 24 dias despues de la irradiacion se registro un restablecimiento del numero de globulos blancos. El indice de trombocitos disminuyo en ambas especies, un poco antes en el perro que en la oveja. En ambas especies, a la tercera semana a contar de la irradiacion, se observo que se restablecian los valores normales en los animales expuestos a los neutrones, pero no en aquellos sometidos a la accion de los rayos X. En ambos grupos de perros, al noveno dia se registro una reduccion importante del indice hematocrito, pero no ocurrio lo mismo con ninguno de los grupos de ovejas expuestos. Como parametro para la determinacion de la funcion hematopoyetica, se determinaron los indices de depuracion plasmatica del {sup 59}Fe en los sujetos estudiados. Los autores estudian la posibilidad de aplicar las alteraciones de este

  12. Determination of the fast neutrons spectra by the Elastic scattering method (n, p); Determinacion del espectro de neutrones rapidos por el metodo de la dispersion elastica (n, p)

    Energy Technology Data Exchange (ETDEWEB)

    Elizalde D, J

    1973-07-01

    This work consists in determining the fast neutron spectra emitted by a Pu-Be isotopic source. The implemented technique is based in the spectrometry (n, p). This consists in making to fall on a fast neutrons beams (polyenergetic) over a thin film of hydrogenated material, detecting the spectra of emitted protons at a fix angle. The polyethylene film and the used solid state detector are inside of a vacuum chamber. The detector is placed at 30 degree with respect to direction of the incident neutrons beam. The protons spectra is stored in a multichannel. the energy is obtained with the prior calibration of the system. The data processing involves the transformation of the protons spectra observed at the falling on neutrons spectra over the film. The energy of the neutrons is related with that of the protons, according to the collision kinematical equations. The cross section of elastic collision of the neutrons with the hydrogen atoms is obtained from literature. Applying these relations to the observed spectra it is obtained the falling on neutron spectra over the film. (Author)

  13. Manganese determination om minerals by activation analysis, using the californium-252 as a neutron source; Determinacao de manganes em minerios, por analise por ativacao, usando californio-252 como fonte de neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Cardoso, Antonio

    1976-07-01

    Neutron Activation Analysis, using a Californium-252 neutron source, has been applied for the determination of manganese in ores such as pyrolusite, rodonite (manganese silicate)' and blending used in dry-batteries The favorable nuclear properties of manganese, such as high thermal neutron cross-section for the reaction {sup 55}Mn (n.gamma){sup 56} Mn, high concentration of manganese in the matrix and short half - life of {sup 56}Mn, are an ideal combination for non-destructive analysis of manganese in ores. Samples and standards of manganese dioxide were irradiated for about 20 minutes, followed by a 4 to 15 minutes decay and counted in a single channel pulse-height discrimination using a NaI(Tl) scintillation detector. Counting time was equal to 10 minutes. The interference of nuclear reactions {sup 56}Fe(n,p){sup 56}Mn and {sup 59} Co (n, {alpha}){sup 56} were studied, as well as problems in connection with neutron shadowing during irradiation, gamma-rays attenuation during counting and influence of granulometry of samples. One sample,was also analysed by wet-chemical method (sodium bismuthate) in order to compare results. As a whole, i t was shown that the analytical method of neutron activation for manganese in ores and blending, is a method simple, rapid and with good precision and accuracy. (author)

  14. Manganese determination om minerals by activation analysis, using the californium-252 as a neutron source; Determinacao de manganes em minerios, por analise por ativacao, usando californio-252 como fonte de neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Cardoso, Antonio

    1976-07-01

    Neutron Activation Analysis, using a Californium-252 neutron source, has been applied for the determination of manganese in ores such as pyrolusite, rodonite (manganese silicate)' and blending used in dry-batteries The favorable nuclear properties of manganese, such as high thermal neutron cross-section for the reaction {sup 55}Mn (n.gamma){sup 56} Mn, high concentration of manganese in the matrix and short half - life of {sup 56}Mn, are an ideal combination for non-destructive analysis of manganese in ores. Samples and standards of manganese dioxide were irradiated for about 20 minutes, followed by a 4 to 15 minutes decay and counted in a single channel pulse-height discrimination using a NaI(Tl) scintillation detector. Counting time was equal to 10 minutes. The interference of nuclear reactions {sup 56}Fe(n,p){sup 56}Mn and {sup 59} Co (n, {alpha}){sup 56} were studied, as well as problems in connection with neutron shadowing during irradiation, gamma-rays attenuation during counting and influence of granulometry of samples. One sample,was also analysed by wet-chemical method (sodium bismuthate) in order to compare results. As a whole, i t was shown that the analytical method of neutron activation for manganese in ores and blending, is a method simple, rapid and with good precision and accuracy. (author)

  15. Elementary composition of the siderurgy slag by instrumental neutron activation analysis; Composicao elementar em escoria de siderurgia por analise por ativacao neutronica instrumental

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Helder de; Piau, Wilson Caixeta; Mortatti, Jefferson [Centro de Energia Nuclear na Agricultura (CENA), Piracicaba, SP (Brazil); Sarries, Gabriel Adrian [Sao Paulo Univ., Piracicaba, SP (Brazil). Escola Superior de Agricultura Luiz de Queiroz

    2000-07-01

    The slag has been applied to the ground to neutralize its acidity, in similar way to the calcareous rock, contributing in the agriculture as corrective of the acidity alone it and source of nutrients for the plants. However, the alternative for the agricultural slag exploitation is related to metal texts heavy gifts in the slag. The objective of the present work was to survey of the chemical composition of trashes generated in blast high-oven, steel, oven of pan and fertilizers that had used in its manufacture slag of siderurgy for the technique of instrumental neutron activation analysis. The results had evidenced the existence of high variations in the elements Ce, Cr, In, K, Sb and Zn in the distinct analyzed samples. (author)

  16. Study of damages by neutron irradiation in lithium aluminates; Estudio de danos por irradiacion neutronica en aluminatos de litio

    Energy Technology Data Exchange (ETDEWEB)

    Palacios G, O

    1999-06-01

    Lithium aluminates proposed to the production of tritium in fusion nuclear reactors, due to the thermal stability that they present as well as the behavior of the aluminium to the irradiation. As a neutron flux with profile ({approx_equal} 14 Mev) of a fusion reactor is not available. A irradiation experiment was designed in order to know the micro and nano structure damages produced by fast and thermal neutrons in two irradiation positions of the fusion nuclear reactor Triga Mark III: CT (Thermal Column) and SIFCA (System of Irradiation Fixed of Capsules). In this work samples of lithium aluminate were characterized by XRD (X-Ray Diffraction), TEM (Transmission Electron Microscopy) and SEM (Scanning Electron Microscopy). Two samples were prepared by two methods: a) coalition method and b) peroxide method. This characterization comprised original and irradiated samples. The irradiated sample amounted to 4 in total: one for each preparation method and one for each irradiation position. The object of this analysis was to correlate with the received neutron dose the damages suffered by the samples with the neutron irradiation during long periods (440 H), in their micro and nano structure aspects; in order to understand the changes as a function of the irradiation zone (with thermal and fast neutron flux) and the preparation methods of the samples and having as an antecedent the irradiation in SIFCA position by short times (2h). The obtained results are referred to the stability of {gamma} -aluminate phase, under given conditions of irradiation and defined nano structure arrangement. They also refer to the proposals of growth mechanism and nucleation of new phases. The error associated with the measurement of neutron dose is also discussed. (Author)

  17. Determination of radiation levels by neutrons in an accelerator for radiotherapy; Determinacion de niveles de radiacion por neutrones en un acelerador para radioterapia

    Energy Technology Data Exchange (ETDEWEB)

    Paredes G, L.; Salazar B, M.A. [Instituto Nacional de Investigaciones Nucleares, Apdo. Postal 18-1027, 11801 Mexico D.F. (Mexico); Genis S, R. [Fundacion Clinica Medica Sur, Puente de Piedra 150, Col. Torriello Guerra, Tlalpan 14050, Mexico D.F. (Mexico)

    1998-12-31

    It was determined the radiation levels by neutrons due to photonuclear reactions ({gamma}, n) which occur in the target, levelling filter, collimators and the small pillow blinding of a medical accelerator Varian Clinac 2100C of 18 MeV, using thermoluminescent dosemeters UD-802AS and US-809AS. The experimental values were presented for the patient level, inside and outside of the radiation field, as well as for the small pillow. (Author)

  18. Neutron activation analysis of alternative phosphate rocks used in animal nutrition; Analise por ativacao neutronica por fontes alternativas de fosforo para a nutricao animal

    Energy Technology Data Exchange (ETDEWEB)

    Canella, Artur A.; Ferreira, Walter M. [Minas Gerais Univ., Belo Horizonte, MG (Brazil). Escola de Veterinaria]. E-mail: avelara@ufmg.br; Menezes, Maria Angela de B.C. [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil)]. E-mail: menezes@cdtn.br

    2005-07-01

    Since 1980's, Bovine Sponghiform Encephalophaty has insidiously created a fierce battleground between farmers, scientists, environmentalists and consumers. The use of meat and bone meals is currently prohibited in ruminant feeds throughout the world. Some inorganic sources offer the combination of high phosphorus content and acceptable animal digestibility make them options as supplemental phosphorus, for instance phosphate rocks, general term applied to minerals valued chiefly for their phosphorus content. However, phosphate rocks are long been known containing hazardous elements, make them sometimes unsuitable for animal nutrition. Neutron Activation Analysis has been supportive to the mineral evaluation of alternative phosphate rocks. This evaluation is subject of on-going doctoral thesis which has been carried-out by the main author. The NAA method has been very efficient due to its highly sensitive and multi-elemental nature. In this paper results of Vanadium content from three different phosphate rocks are presented. Their values have been pointed out that Brazilian phosphate rocks present hazardous elements at the same levels of phosphate rocks from some countries of Africa, North America and Middle East, data from our study (Brazilian data) and FAO - Food and Agriculture Organization (others countries). (author)

  19. Determination of essential elements in edible seaweed by neutron activation analysis; Determinacao de elementos essenciais em algas marinhas comestiveis por analise por ativacao neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Alves, Cassio Bessa Lima; Maihara, Vera Akiko, E-mail: cassio_man@hotmail.com, E-mail: vmaihara@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    Comestible marine algae are gaining wider global trade, not only because of the taste but also the nutritional quality they present. They are rich in protein, fiber, vitamins and are excellent sources of essential elements due to their ability to absorb substances storing them in their bodies. its chemical composition varies according to the species, habitat, maturity and environmental conditions which are submitted. The method of Neutron Activation Analysis was used to determine the essential elements Cl, K, Mg, Mn and Na present in marine algae from different countries, which are sold in the city of Sao Paulo. A total of 6 samples of marine algae were analyzed, 4 species of Nori (Porphyra umbilicates) from China, Korea, Japan and USA; 1 of Hijiki (Hijikia fusiforme) species from Japan; and 1 species of Kombu (Laminaria sp.) of South Korea. To validate the methodology used was the reference material NIST SRM 1577b Bovine Liver. The concentrations range from 5265-1175 μg/g to CL; from 14413-90261 μg/g to K; from 3007-7091 μg/g to Mg; from 2,3-33,8 μg/g to Mn and from 5161-24973 μg/g to Na.

  20. Determination of micro minerals in phosphorus source fed to animals by activation with neutrons; Determinacao de microminerais em fontes de fosforo fornecidas a animais por ativacao com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Armelin, Maria Jose A.; Mori, Clara S. [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil); Silva, Jose Cleto da [Centro de Energia Nuclear na Agricultura (CENA), Piracicaba, SP (Brazil)

    1995-12-31

    Instrumental neutron activation analysis was applied to determine the elements Ca, Co, Cr, Cu, Eu, Fe, K, La, Mg, Mn, Na, P, Sb, Sc and Zn in four phosphatic supplementation samples. analysis of variance, Turkey`s and Sheffe`s test were applied to certify the homogeneity of the sub-samples (200 mg). In general, the precision of the method was lower than 15%. The phosphatic supplementation samples analyzed can be considered adequate to feed into animals in relation to mineral composition. (author). 5 refs., 2 tabs.

  1. Trace element determination in human bones using the neutron activation analysis method; Determinacao de elementos traco em ossos humanos pelo metodo de analise por ativacao com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Kramarski, Sila; Saiki, Mitiko [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil); Borelli, Aurelio [Sao Paulo Univ., SP (Brazil). Faculdade de Medicina. Lab. de Nutricao Humana; Batalha, Joao R.F. [Universidade de Mogi das Cruzes, SP (Brazil). Faculdade de Medicina

    1997-10-01

    This work presents the results obtained in the analysis of rib bone samples from normal human individuals by applying instrumental neutron activation analysis. In these analyses, the elements Br, Cl, Fe, K, Mg, Na, Rb, Sr and Zn were found at the ppm level and the elements Ca and P at the level of percentage. The precision and the of the results were evaluated by using biological reference materials NIST SRM 1577a Bovine Liver, IAEA A-11 Milk powder, NIES CRM 9 Sargasso e NIES CRM 10A Rice Flour Unpolished. (author). 5 refs., 3 tabs.

  2. Studies of trace element determinations in nails by neutron activation analysis method; Estudo de elementos traco em unhas pelo metodo de analise por ativacao com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Aguiar, Amilton Reinaldo; Saiki, Mitiko [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

    1996-07-01

    The purpose of this work was to develop the neutron activation analysis for trace element determinations in nails in order to apply this method to the study of the cystic fibrosis disease. It was verified that the elements Al, As, Br, Ca, Cd, Cl, Co, Cr, Cu, Fe, K, Mg, Mn, Na, Se and Zn can be determined by using short and long irradiations with thermal neutron flux from 10{sup 11} to 10{sup 13} n.cm{sup -2}.{sup -1} at the IEA-R1 nuclear research reactor. The washing solutions of triton-X100, NH{sub 4} OH and acetone were tested in order to eliminate external contaminants from the nail samples. The nail analyses of the individual fingers from both of hands showed that the samples must be collected from all the fingers from both of hands to have a representative sample. The precision and the accuracy of the results were also examined by analyzing NIES 10C Rice Flour, IUPAC Bowen's Kale and NIST 1572 Citrus Leaves reference materials. (author)

  3. Considerations for boron neutron capture therapy studies; Consideracoes sobre o estudo da BNCT (terapia de captura neutronica por boro)

    Energy Technology Data Exchange (ETDEWEB)

    Faria Gaspar, P de

    1994-12-31

    Radiotherapy is indispensable as a mean to eradicate deeply or infiltrating tumor tissue that can not be removed surgically. Therefore, it is not selective and may also kill the surrounding health tissue. The principle of BNCT (Boron Neutron Capture Therapy) consist in targeting a tumor selectively with a boron-10 compound. This nuclide has a large capture cross section for thermal neutrons and the nuclear reaction and the delivered energy in locus will selective the tumor. Since its initial proposal in 1963 BNCT has made much progress, however it is not used in a routine treatment. In this work it was approached some complex procedures, as the obtention of selective boron compounds, the adequate set up of neutron beams, the biodistribution, the in vivo and in vitro studies, and also human patients treatments. This work provide fundamentals about BNCT to professional of different areas of knowledge since it comprises multidisciplinary study. It includes appendixes for the ones not related to the field for a better comprehension of the many aspects involved. It is also presented a glossary containing technical and basic aspects involved. It is also presented a glossary containing technical and basic terms referred in the work. (author). 174 refs, 1 fig, 12 apps.

  4. Anti mutagenesis of chemical modulators against damage induced by reactor thermal neutrons; Antimutagenesis de moduladores quimicos contra el dano inducido por neutrones termicos de reactor

    Energy Technology Data Exchange (ETDEWEB)

    Zambrano A, F.; Guzman R, J.; Garcia B, A.; Paredes G, L.; Delfin L, A. [Instituto Nacional de Investigaciones Nucleares, Departamentos de Materiales Radiactivos, de Biologia, del Reactor y Gerencia de Aplicaciones Nucleares en la Salud, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1999-07-01

    The mutations are changes in the genetic information whether for spontaneous form or induced by the exposure of the genetic material to certain agents, called mutagens: chemical or physical (diverse types of radiations). As well as exist a great variety of mutagens and pro mutagens (these last are agents which transform themselves in mutagens after the metabolic activation). Also several chemical compounds exist which are called antimutagens because they reduce the mutagens effect. The C vitamin or ascorbic acid (A A) presents antimutagenic and anti carcinogenic properties. On the other hand a sodium/copper salt derived from chlorophyll belonging to the porphyrin group (C L) contains a chelated metal ion in the center of molecule. It is also an antioxidant, antimutagenic and anti carcinogenic compound, it is called chlorophyllin. The objective of this work is to establish if the A A or the C L will reduce the damages induced by thermal and fast reactor neutrons. (Author)

  5. Neutron spectrometry and dosimetry by means of evolutive neural networks; Espectrometria y dosimetria de neutrones por medio de redes neuronales evolutivas

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz R, J.M.; Martinez B, M.R.; Vega C, H.R. [UAZ, Av. Ramon Lopez Velarde Num. 801, 98000 Zacatecas (Mexico)

    2008-07-01

    The artificial neural networks and the genetic algorithms are two relatively new areas of research, which have been subject to a growing interest during the last years. Both models are inspired by the nature, however, the neural networks are interested in the learning of a single individual, which is defined as fenotypic learning, while the evolutionary algorithms are interested in the adaptation of a population to a changing environment, that which is defined as genotypic learning. Recently, the use of the technology of neural networks has been applied with success in the area of the nuclear sciences, mainly in the areas of neutron spectrometry and dosimetry. The structure (network topology), as well as the learning parameters of a neural network, are factors that contribute in a significant way with the acting of the same one, however, it has been observed that the investigators in this area, carry out the selection of the network parameters through the essay and error technique, that which produces neural networks of poor performance and low generalization capacity. From the revised sources, it has been observed that the use of the evolutionary algorithms, seen as search techniques, it has allowed him to be possible to evolve and to optimize different properties of the neural networks, just as the initialization of the synaptic weights, the network architecture or the training algorithms without the human intervention. The objective of the present work is focused in analyzing the intersection of the neural networks and the evolutionary algorithms, analyzing like it is that the same ones can be used to help in the design processes and training of a neural network, this is, in the good selection of the structural parameters and of network learning, improving its generalization capacity, in such way that the same one is able to reconstruct in an efficient way neutron spectra and to calculate equivalent doses starting from the counting rates of a Bonner sphere

  6. Chemical Production using Fission Fragments; Emploi des fragments de fission dans la production de substances chimiques; Ispol'zovanie produkto v raspada v khimicheskom proizvodstve; Empleo de los fragmentos de fision en la industria quimica

    Energy Technology Data Exchange (ETDEWEB)

    Dawson, J K; Moseley, F [AERE, Harwell (United Kingdom)

    1960-07-15

    'eau. Aucun des systemes etudies jusqu'a present ne parait offrir de possibilites interessantes pour la grande industrie chimique. (author) [Spanish] En una memoria presentada en la segunda Conferencia Internacional sobre la Utilizacion de la Energia Atomica con Fines Pacificos [A/Conf. 15/P. 76] se expusieron algunas consideraciones , atendiendo al diseno de los reactores, sobre la utilizacion de la energia de retroceso de los fragmentos de fision para la produccion de ciertos compuestos quimicos de importancia industrial. La presente memoria pasa revista a los progresos realizados desde entonces en esta materia por el Atomic Energy Research Establishment de Harwell. Los autores examinan la relacion entre el alcance y la energia para los fragmentos de fision al discutirse la eleccion del combustible para un reactor destinado a la produccion de compuestos quimicos y describen la variacion de efecto quimico observada a lo largo de la trayectoria de los fragmentos de fision en la irradiacion de mezclas de nitrogeno y oxigeno. Analizan tambien los resultados de investigaciones recientes acerca de los efectos de fragmentos de fision sobre mezclas de monoxido de carbono e hidrogeno y sobre el vapor de agua. Al parecer, ninguno de los sistemas estudiados hasta la fecha ofrece perspectivas particularmente interesantes para la industria quimica pesada. (author) [Russian] V doklade, predstavlennom ran'she na Vtoroj mezhdunarodnoj konferentsii Organizatsii Ob'edinennykh Natsij po mirnomu ispol'zovaniyu atomnoj ehnergii (A/Conf. 15/P. 76) v svyazi s konstruktsiej reaktorov obsuzhdalis' nekotorye soobrazheniya otnositel'no vozmozhnosti ispol'zovaniya ehnergii otdachi produktov raspada dlya proizvodstva vazhnykh dlya promyshlennosti khimikaliev. V nastoyashchem doklade rezyumiruyutsya bolee nedavnie rezul'taty, dostignutye v ehtoj oblasti Nauchno-issledo-vatel'skim institutom po atomnoj ehnergii v KHaruehlle. Sootnoshenie mezhdu prokhodimym rasstoyaniem i ehnergiej produktov deleniya

  7. Analysis by Neutron activation of the Calakmul jadeite mask; Analisis por activacion neutronica de la mascara de jadeita de Calakmul

    Energy Technology Data Exchange (ETDEWEB)

    Alemon A, E.; Herrera V, L. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1998-07-01

    It is very important to know the elemental composition of archaeological materials with the purpose to find relations that allow to establish their origin standards. the origin and present localization of pre hispanic archaeological pieces can lead to the determination of commercial routes and of technology transfer among different ancient cultures. In the present work it has been realized a systematic analysis using the Instrumental neutron activation analysis technique of three samples obtained from Calakmul jadeite mask, tomb I, that in addition to give a composition of constituent and trace elements detected by this technique it has leaded to establish an applicable methodology to the routine analysis of ceramics of historical interest. (Author)

  8. Determination of mercury in dentists through Neutron activation analysis; Determinacion de mercurio en odontologos mediante Analisis por activacion neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Padilla M, M.A.; Granados C, F. [Instituto Nacional de Investigaciones Nucleares, Departamento de Quimica, A.P. 18-1027, C.P. 11801 Mexico D.F. (Mexico)

    2000-07-01

    It was determined the mercury levels in urine through Neutron activation analysis to 25 dentists who have been exposed to mercury by several time periods, because of the routine manipulations of amalgams. The determined concentrations of mercury were less to 10 {mu} g Hg/l of urine. The results were founded inside the safety limits reported in the literature. The mercury levels in the dentists are associated with a wide variety of factors that contribute to their exposure as: number of years of dental practice, number of amalgams manipulated between others. (Author)

  9. Determination of selenium in biological material by instrumental neutron activation analysis using {sup 77m} Se radioisotope; Determinacao de selenio em materiais biologicos por analise por ativacao com neutrons instrumental usando o radioisotopo {sup 77m} Se

    Energy Technology Data Exchange (ETDEWEB)

    Vasconcellos, Maria B.A.; Moreira, Edson G.; Catharino, Marilia G.M.; Tokura, Alexandra M.; Saiki, Mitiko [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil). Supervisao de Radioquimica

    1999-11-01

    Selenium is an essential element in human diet due to its relation to the protection against carcinogenic substances, heart disease, hypertension, sexual performance enhancement, and others. In this work Se concentration in samples of the biological certificate reference materials Human Hair BCR-CRM 397, Spiked Human Hair IAEA-085, Unspiked Human Hair IAEA-086; Dogfish Liver DOLT-1 and Dogfish Muscle DORM-1 were determined in order to improve the instrumental neutron activation analysis, INAA, method using {sup 77m} Se radioisotope. The application of this method allows the analysis of a large number of samples of samples with reduced time of experimental and cost. the best results were obtained with the reactor operating at 5 MW and time of irradiation between 10 and 20 s. In these experimental conditions the relative standard deviation and error were generally lower than 10%. (author) 5 refs., 7 tabs.

  10. Trace element determination study in human hair by neutron activation analysis; Estudo da determinacao de elementos traco em cabelos humanos pelo metodo de analise por ativacao com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Frazao, Selma Violato

    2008-07-01

    Human hair analysis studies have been subject of continuous interest due to the fact that they can be used as an important tool to evaluate trace element levels in the human body. These determinations have been carried out to use hair for environmental and occupational monitoring, to identify intoxication or poisoning by toxic metals, to assess nutritional status, to diagnose and to prevent diseases and in forensic sciences. Although hair analysis presents several advantages over other human tissue or fluid analyses, such as organ tissue, blood, urine and saliva, there are some controversies regarding the use of hair analysis data. These controversies arise from the fact that it is difficult to establish reliable reference values for trace elements in hair. The purpose of this study was to evaluate the factors that affect element concentrations in hair samples from a population considered healthy and residing in the Sao Paulo metropolitan area. The collected human head hair was cut in small pieces, washed, dried and analyzed by neutron activation analysis (NAA). Aliquots of hair samples and synthetic elemental standards were irradiated at the IEA-R1 nuclear research reactor for 16 h under a thermal neutron flux of about 5x10{sup 12} n cm{sup -2} s{sup -1} for As, Br, Ca, Co, Cr, Cs, Cu, Fe, K, La, Na, Sb, Sc, Se and Zn determinations. The induced gamma activities of the standards and samples were measured using a gamma ray spectrometer coupled to an hiperpure Ge detector. For quality control of the results, IAEA- 85 Human Hair and INCT-TL-1 Tea Leaves certified reference materials (CRMs) were analyzed. Results obtained in these CRMs presented for most of elements, good agreement with the values of the certificates (relative errors less than 10%) and good precision (variation coefficients less than 13.6%). Results of replicate hair sample analysis showed good reproducibility indicating homogeneity of the prepared sample. Results obtained in the analyses of dyed and

  11. Determination of essential elements in dietetic sample by neutron activation analysis; Determinacao de elementos essenciais em alimentos dieteticos pela tecnica de analise por ativacao com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Siquelli, Murilo V.; Maihara, Vera A. Maihara [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil). Lab. de Analise por Ativacao Neutronica]. E-mail: murilo_siquelli@hotmail.com; vmaihara@ipen.br

    2005-07-01

    In the last years there has been an increase of the dietetic product consumption by people who suffer from diabetes, heart disease and by people concerned about having a healthy life as well. Despite the increase of dietetic product presents in the diet of the Brazilian population, the use of these products is still controversial. The analysis of the nutritional composition of these products is becoming important because a great number of people is changing their traditional food by dietetic products. In the literature, there is no information about the inorganic composition, mainly related to the essential elements, in the dietetic products: diet and light . In this study are presented preliminary results of the concentrations of Br, Ca, Cr, Fe, Na and Zn determined by Instrumental Neutron Activation Analysis in aspartame, saccharin and cyclamate sodium , and stevia based sweetener samples. Gelatin samples, diet and light, were also analyzed. Methodology validation was done analyzing NIST reference materials Tea Leaves (INCT-TL-1) and Mixed Polish Herbs (INCT-MPH-2). (author)

  12. Determination of rare earth elements in biomonitors by neutron activation; Determinacao de elementos terras raras em biomonitores por ativacao neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Figueiredo, Ana M.G.; Saiki, Mitiko; Ticianelli, R.B. [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil); Domingos, M.; Alves, E.S.; Marcelli, M.P. [Instituto de Botanica, Sao Paulo, SP (Brazil)

    2000-07-01

    The rare earth elements (REE) are becoming more and more important from the technological point of view, due to their increasing use in modern industry. Due to this fact, environmental contamination by REE may become significant, and little information are still available about biological effects of REE in plants, animals and human beings. The use of biomonitors to control environmental pollution has been an ecological and economical alternative in Europe and United Sates, to minimize the high costs of conventional equipment s. In the present paper, neutron activation analysis was employed to determine La, Ce, Nd, Sm, Eu, Tb, Yb and Lu in the lichen Canoparmelia texana and in Tillandsia usneoides, species that have been widely used as monitors of atmospheric pollution. The results showed an accumulation of REE in the biomonitors, indicating good possibilities of their utilization in the study of environmental contamination by REE. (author)

  13. Semiautomatic exchanger of samples for carry out neutron activation analysis; Intercambiador semiautomatico de muestras para realizar analisis por activacion neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar H, F.; Quintana C, G. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Torres R, C. E.; Mejia J, J. O., E-mail: fortunato.aguilar@inin.gob.mx [Instituto Tecnologico de Toluca, Av. Tecnologico s/n, Ex-Rancho La Virgen, Metepec, Estado de Mexico (Mexico)

    2015-09-15

    In this paper the design methodology and implementation of a semiautomatic exchanger of samples for the Analysis Laboratory by Neutron Activation of the Reactor department is presented. Taking into account the antecedents, the necessities of improvement are described, as well as the equipment that previously contained the Laboratory. The project of the semiautomatic exchanger of samples was developed at Instituto Nacional de Investigaciones Nucleares, with its own technology to increase independence from commercial equipment. Each element of the semiautomatic exchanger of samples is described both in the design phase as construction. The achieved results are positive and encouraging for the fulfillment of the proposed objective that is to increase the capacity of the Laboratory. (Author)

  14. 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

    The production of radiophosphorus by the fast neutron (n, p) reaction on sulphur is used for the determination of sulphur by activation analysis. Using this technique it is possible to determine sulphur in materials of high thermal-neutron absorption cross-section because the absorption cross-sections for fast neutrons are, in general, much lower than those for slow neutrons, so that self-shielding errors are considerably reduced. Interference due to the slow neutron (n, {gamma}) reaction on neutral phosphorus is eliminated by a double irradiation technique involving irradiation in regions of differing slow/fast flux-ratios. The method has been applied to the determination of sulphur in chromium and arsenic. (author) [French] La production de radiophosphore par reaction (n, p) de neutrons rapides sur le soufre est utilisee pour la determination du soufre au moyen d'une analyse par activation. Cette methode permet la determination du soufre dans les matieres de forte section efficace d'absorption des neutrons thermiques; en effet, les sections efficaces d'absorption des neutrons rapides sont, d'une maniere generale, beaucoup plus faibles que pour les neutrons lents, de sorte que les erreurs d'autoprotection se trouvent considerablement reduites. L'interference due a la reaction (n, {gamma}) des neutrons lents sur le phosphore naturel est eliminee par une double irradiation, qui implique une irradiation dans les regions ou le rapport du flux de neutrons lents au flux de neutrons rapides a des valeurs differentes. La methode a ete appliquee a la determination du soufre dans le chrome et l'arsenic. (author) [Spanish] La formacion de fosforo radiactivo por la accion de los neutrones rapidos sobre el azufre, reaccion (n, p), puede servir para determinar este elemento mediante analisis por activacion. El empleo de esta tecnica permite efectuar determinaciones de azufre en materiales de elevada seccion eficaz de absorcion de neutrones termicos porque, en general, las

  15. Determination of essential and toxic elements in commercial baby foods by instrumental neutron activation analysis and atomic absorption spectrometry; Determinacao dos elementos essenciais e toxicos em alimentos comerciais infantis por analise por ativacao com neutrons e espectrometria de absorcao atomica

    Energy Technology Data Exchange (ETDEWEB)

    Vallinoto, Priscila

    2013-08-01

    The World Health Organization recommends that infants should be breast fed exclusively for at least six months after birth. After this period, it is recommended to start introducing complementary foods, in order to meet the child's nutritional, mineral and energy needs. Commercial food products for infants form an important part of the diet for many babies. Thus, it is very important that such food contains sufficient amounts of minerals. Inadequate complementary feeding is a major cause of high rates of infant malnutrition in developing countries. In this study, essential elements: Ca, Cl, Co, Cr, Fe, K, Mg, Mn, Na, Se and Zn and toxic elements: As, Cd, Hg levels were determined in twenty seven different commercial infant food product samples by Instrumental Neutron Activation Analysis (INAA) and Atomic Absorption Spectrometry (AAS). In order to validate both methodologies the reference material: INCT MPH-2 Mixed Polish Herbs and NIST - SRM 1577b Bovine Liver by INAA and NIST - SRM 1548th Typical Diet and NIST - SRM 1547 Peach Leaves by AAS were analyzed. The twenty seven baby food samples were acquired from Sao Paulo city supermarkets and stores. Essential and toxic elements were determined. Most of the essential element concentrations obtained were lower than the World Health Organization requirements, while concentrations of toxic elements were below the tolerable upper limit. These low essential element concentrations in these samples indicate that infants should not be fed only with commercial complementary foods. (author)

  16. Moderation of Neutrons Emitted by a Pulsed Source and Neutron Spectrometry Based on Slowing-Down Time; Ralentissement des Neutrons Emis par une Source Pulsee et Leur Spectrometrie en Fonction du Temps de Ralentissement; Zamedlenie nejtronov, ispuskaemykh impul'snym istochnikom, i spektrometriya nejtronov po vremeni zamedleniya; Moderacion de Neutrones Emitidos por una Pitente Pulsada y Espectrometria Neutronica Basada en el Tiempo de Frenado

    Energy Technology Data Exchange (ETDEWEB)

    Bergman, A. A.; Isakov, A. I.; Kazarnovskij, M. V.; Popov, Ju. P.; Shapiro, F. L. [Fizicheskij Institut Im. P.N. Lebedeva AN SSSR, Moskva, SSSR (Russian Federation)

    1965-08-15

    ralentissement, les variations de la section efficace des reactions neutroniques en fonction de l'energie et ils examinent les possibilites d'application et de perfectionnement qu'offre cette methode de spectrometrie. Ils etudient brievement les resultats de deux sortes de mesures spectrometriques: 1. Mesures precises portant sur les variations, en fonction de l'energie, des rapports entre les sections efficaces des reactions He{sup 3}(n, p), Li{sup 6}(n, {alpha}), B{sup 10}(n, {alpha}) et N{sup 14}(n, p). Le resultat le plus interessant de ces experiences a ete de decouvrir une composante negative constante de la section efficace de ces reactions et de trouver des indices laissant supposer l'existence d'un niveau excite de {sup 4}He. 2. Mesures de la variation que subissent les valeurs moyennes des sections efficaces de capture radiative des neutrons par les noyaux, en fonction de l'energie. Ces mesures, qui ont ete faites pour un grand nombre de substances, notamment pour divers isotopes, ont permis de constater l'existence de plusieurs niveaux de resonance a faible largeur neutronique, auparavant inconnues, et de determiner pour beaucoup de noyaux la valeur de la fonction de force relative a la capture des neutrons a moment orbital 1= 1. (author) [Spanish] Durante los ultimos diez anos se han venido realizando en el Instituto de Fisica p. N. Lebedev investigaciones sobre la moderacion no estacionaria de neutrones en medios pesados, el desarrollo de un metodo de espectrometria neutronica basada en la medicion del tiempo de frenado y la aplicacion de este metodo al estudio de la relacion entre la energia y las secciones eficaces de las reacciones nucleares producidas por neutrones con niveles energeticos de hasta 30 keV, En la presente memoria los autores pasan revista a dichos trabajos y analizan los resultados obtenidos. Despues de exponer brevemente la teoria de la moderacion y termalizacion no estacionarias de neutrones, los autores presentan los resultados de estudios

  17. Tritium extraction from neutron-irradiated lithium aluminate.; Extraccion del tritio generado por irradiacion neutronica de aluminato de litio.

    Energy Technology Data Exchange (ETDEWEB)

    Garcia H, F

    1995-10-01

    Lithium aluminate is being strongly considered as a breeder material because of its thermophysical, chemical and mechanical stability at high temperatures and its favorable irradiation behavior. Furthermore, it is compatible with other blanket and structural materials. In this work, the effects of calcination temperature during preparation, extraction temperature and sweep gas composition were observed. Lithium aluminate prepared by four different methods, was neutron irradiated for 30 minutes at a flux of 10{sup 12} -10{sup 13} n/cm{sup 2} s in the TRIGA Mark III reactor at Salazar, Mexico; and the tritium extraction rate was measured. Calcination temperature do not affect the tritium extraction rate. However, using high calcination temperature, gamma lithium aluminate was formed. The tritium extraction at 600 Centigrade degrees was lower than at 800 Centigrade degrees and the tritium amount extracted by distillation of the solid sample was higher. The sweep gas composition showed that tritium extraction was less with Ar plus 0.5 % H{sub 2} that with Ar plus 0.1 % H{sub 2}. This result was contrary to expected, where the tritium extraction rate could be higher when hydrogen is added to the sweep gas. Probably this effect could be attributed to the gas purity. (Author).

  18. 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)

  19. Neutron Investigation of Magnon Spectrum in Haematite; Etude du Spectre de Magnons dans l'Hematite, au Moyen des Neutrons; Nejtronnoe issledovanie spektra magnona v gematite; Estudio, por Metodos Neutronicos, del Espectro de Magnones en la Hematita

    Energy Technology Data Exchange (ETDEWEB)

    Dimitrijevic, Z.; Rzany, H.; Todorovic, J.; Wanic, A. [Institute for Nuclear Physics Cracow (Poland)

    1965-04-15

    'existence d'une branche optique qui, toutefois, ne se prete pas aux recherches par la methode de la diffusion des neutrons. (author) [Spanish] Los autoresrealizaron sus mediciones en el reactor RA de Vinca con ayuda de un espectrometro neutronicode cristal. Los neutrones monocromaticos ({lambda} = 1.314A) se dispersaron en un monocristal de hematita (Fe{sub 2}O{sub 3}{alpha}) de gran tamano. Se estudiaron las distribuciones angulares de los neutrones inelast Lea mente dispersos, midiendo para un cierto numero de angulos distintos de desplazamiento del cristal, {Delta}{theta}, la anchura {Gamma} del haz de neutrones dispersos (el llamado cono de dispersion), que fue adscrito a la superficie de dispersion magnOnica que envolvia al punto(l,l,l)delared reciproca. Se calcularon y compararon con los puntos obtenidos experimentalmente los valores de {Gamma} en funcion de la variacion del angulo de desplazamiento para diversas velocidades de los magnones. Se comprobo que el valor de la velocidad en la direccion [111] era igual a 25,5 {+-} 1,0 km/s, descubriendose asi la anisotropia estructural de la relacion de dispersion magnonica. Se encontro que la velocidad era superior para las direcciones de propagacion paralelas al eje [111], lo que esta cualitativamente de acuerdo con anteriores mediciones (Riste y otros) que daban una velocidad v = 38 km/s. No fue posible poner de manifiesto la existencia de una laguna energetica Eg en la banda de las energias magnonicas acusticas. Se calculo que el valor de Eg tiene que ser inferior a 1 meV. Utilizando las formulas propuestas por Wallace se calcularon las relaciones de dispersion de los magnones en la hematita. Este calculo se efectuo en el supuesto de que existan dos integrales de intercambio que no desaparecen: J{sub 1} y J{sub 2}, que indican el acoplamiento energetico de superintercambio entre los spins de los iones hierro proximos, enlazados por un ion oxigeno, los angulos de los enlaces Fe-O-Fe tenidos en cuenta son de 132 Degree

  20. Indirect Determination of Half-Lives of Short-Lived Fission Gases Using a Gas Flow Method; Determination Indirecte des Courtes PeRiodes de Produits de Fission Gazeux, par une Methode a Courant Gazeux; 041a 041e 0421 0412 0415 041d 041d 041e 0415 041e 041f 0420 0415 0414 0415 041b 0415 041d 0418 0415 041f 0415 0420 0418 041e 0414 041e 0412 041f 041e 041b 0423 0420 0410 0421 041f 0410 0414 0410 041a 041e 0420 041e 0422 041a 041e 0416 0418 0412 0423 0429 0418 0425 0413 0410 0417 041e - 041e 0411 0420 0410 0417 041d 042b 0425 041f 0420 041e 0414 0423 041a 0422 041e 0412 0414 0415 041b 0415 041d 0418 042f 0421 0418 0421 041f 041e 041b 042c 0417 041e 0412 0410 041d 0418 0415 041c 041c 0415 0422 041e 0414 041e 0412 0413 0410 0417 041e 0412 041e 0413 041e 041f 041e 0422 041e 041a 0410 ; Determinacion Indirecta del T 1/2 de los Cases de Fision de Periodo Corto por un Metodo de Circulacion

    Energy Technology Data Exchange (ETDEWEB)

    Patzelt, P.; Herrmann, G. [Institut fuer Anorganische Chemie und Kernchemie der Universitaet Mainz, Mainz, Federal Republic of Germany (Germany)

    1965-07-15

    decroissance des pics gamma appropriees. Les chiffres indiques representent les valeurs moyennes d'un certain nombre d'experiences et resultent d'un mode de ponderation tel que W{sub i} Tilde-Operator 1/o{sup 2}. Tous les calculs ont ete effectues au centre d'ordinateurs de l'Universite de Mayence. (author) [Spanish] Dado que el estudio de la distribucion de las cafgas en la fision nuclear requiere la determinacion de los rendimientos primatios de los diferentes productos de fision, que por lo general son de periodo corto o derivan de precursores de periodo corto, es preciso poder llevar a cabo separaciones muy rapidas y eficaces de los eslabones contiguos de una cadena de fision. Aprovechando el poder de emanacion sumamente elevado de ciertos compuestos de uranio, se pueden practicar con gran facilidad separaciones de los gases en mas de una docena de cadenas de productos de fision. Pero el calculo de los rendimientos y del poder de emanacion efectivo de blancos en forma de capas gruesas pueden resultar considerablemente afectados por los datos relativos al periodo de los gases. En consecuencia, los autores han determinado con gran precision los periodos de los isotopos {sup 93}Kr y {sup 131}Xe a {sup 143}Xe aplicando un metodo basado en la velocidad de circulacion de estos gases, junto con una tecnica perfeccionada de carga de electrodos. Efectuaron mediciones basadas en la cantidad de productos activos de desintegracion de periodo largo depositada en los electrodos. La velocidad de circulacion, el tiempo de irradiacion y de enfriamiento, asi como los aparatos de recuento se escogieron de forma que facilitaba grandemente la medicion de cada uno de los productos descendientes. En algunos casos, fue indispensable, por razones de selectividad radioquimica, proceder a separaciones. Los resultados obtenidos son: {sup 89}Kr, 3.11 {+-} 0.06 min: {sup 90}Kr, 32.1 {+-} 0.8 s; {sup 91}Kr, 8.36 {+-} 0.15 s; {sup 92}Kr, 1,92 {+-} 0.07 s; {sup 93}Kr, 1.17 {+-} 0.04 s; {sup 137}Xe, 3

  1. Calculation of the Inelastic Scattering of Neutrons from Polyethylene and Water; Calcul de la diffusion inelastique des neutrons par le polyethylene et l'eau; Raschet neuprugogo rasseyaniya nejtronov poliehtilenom i vodoj; Calculo de la dispersion inelastica de neutrones por polietileno y agua

    Energy Technology Data Exchange (ETDEWEB)

    Goldman, D T; Federighi, F D [Knolls Atomic Power Laboratory, General Electric Company, Schenectady, NY (United States)

    1963-01-15

    quelques precautions lorsque l'on fait l'integration numerique par rapport aux angles et aux energies. Le modele de diffusion a ete etendu aux calculs de la diffusion des neutrons par le polyethylene C{sub n}H{sub 2n}. On note des niveaux analogues a 0,089 eV, 0,182 eV, 0,354 eV et 0,533 eV. Les auteurs ont calcule les sections efficaces diffe- rentielle et totale pour la diffusion et ils ont constate que la seconde est en bon accord avec l'experience a la temperature du laboratoire. Ils ont calcule des noyaux de diffusion pour un certain nombre de temperatures et, chaque fois qu'il etait possible de le faire, ils ont compare les resultats aux experiences. De plus, ils ont calcule les spectres de flux de neutrons et les longueuts de diffusion en se fondant sur les equations de la physique des reacteurs. En comparant ces resultats et les donnees experimentales, on constate que ces mesures integrales donnent au moins des indications generales sur les caracteristiques du systeme de diffusion et qu'il conviendrait de les analyser en tenant compte des resultats detailles relatifs aux sections efficaces different tielles. (author) [Spanish] Nelkin propuso un modelo para calcular la dispersion de neutrones termicos por sistemas quimicos. Con arreglo a este modelo, la dinamica real del sistema dispersante se consideraba compuesta por una serie de movimientos oscilatorios cada uno de los cuales podia describirse por un hamiltoniano que conmuta con los hamiltonianos de los otros movimientos oscilatorios. Ello permitiria; expresar la seccion eficaz diferencial de dispersion en forma cerrada. Los autores han utilizado este modelo para calcular la dispersion de neutrones por el agua. Debe procederse con cierto cuidado al efectuar la integracion numerica respecto del angulo y de la energia. El modelo sella utilizado tambien para calcular la dispersion de neutrones por polietileno (C{sub n}H{sub 2n}). A 0,089 eV, 0,182 eV, 0.354 eV y 0,533 eV, se observan niveles analogos en el

  2. Evaluation of defects induced by neutron radiation in reactor pressure vessels steels; Evaluacion de los defectos inducidos por la radiacion neutronica en los aceros de vasijas

    Energy Technology Data Exchange (ETDEWEB)

    Lopez Jimenez, J

    1978-07-01

    We have developed a method for calculating the production of neutron induced defects (depleted zone and crowdions) in ferritic pressure vessel steels for different neutron spectra. They have been analysed both the recoil primary atoms produced by elastic and inelastic collisions with fast neutrons and the ones produced by gamma-ray emission by thermal neutron absorption. Theoretical modelling of increasing in the ductile-brittle transition temperature of ferritic steels has been correlated with experimental data at irradiation temperature up to 400 degree centigree (Author) 15 refs.

  3. Medición del tiempo de generación de Neutrones Prontos por los Métodos de Feynman y Bennett

    OpenAIRE

    Fiestas Urbina, Carlos Job; Fiestas Urbina, Carlos Job

    1982-01-01

    El propósito principal del presente trabajo es determinar el tiempo de generación de neutrones prontos reducidos, la constante de decaimiento de los neutrones, correspondientes a una reactividad, la eficiencia del detector de neutrones de la segunda cadena de arranque, para el reactor de potencia cero con la configuración nuclear #52; haciendo un análisis estadístico del contaje de neutrones mediante los modelos de Feyman y Bennett. La diferencia de estos métodos radica en que el primero no ...

  4. A Time of flight spectrometer for measurements of double differential neutron scattering cross sections; Montaje de un espectrometro por tiempo de vuelo para la medicion de secciones doble diferenciales de dispersion de neutrones

    Energy Technology Data Exchange (ETDEWEB)

    Padron, I; Dominguez, O; Sarria, P. Sandin, C. [Centro de Estudios Aplicados al Desarrollo Nuclear (CEADEN), La Habana (Cuba)

    1996-05-01

    The time -of-Flight neutron spectrometry technique by associated particle method was improved using a D-T neutron generator at Laboratory of Nuclear Analysis. This technique was implemented for double differential cross section measurements and supported by the IAEA Project CUB/01/005. An stilbene scintillation detector (dia=100 mm, length=50 mm) was used as principal neutron detector detector and was situated outside a hole in the concrete wall. This way the fligth path was extended and the scattered neutron cone accurate collimated throught the 2 m concrete wall. For the associated particle {alpha} detection a thin plastic NE-102 scint illator was used, as well as, two scintilation detectors and a long counter for the neutron flux monitoring. In this TOF neutron spectrometer (3.40 m flight path) a 1.7 nseg. temporal resolution was obtained.

  5. Determination of selenium and zinc in rat plasma by instrumental neutron activation analysis; Determinacion de selenio y zinc en plasma mediante analisis por activacion neutronica instrumental

    Energy Technology Data Exchange (ETDEWEB)

    Munoz A, Luis

    1998-12-31

    To evaluate the effects on the thyroid function when simple or multiple zinc, selenium and iodine deficiency are induced, research was carried out in laboratory animals. For simultaneously determining the Zn and Se concentration in rat plasma, an instrumental neutron activation analysis technique was applied. A clean laboratory, was used for the preparation of samples. High purity materials were used for sample collection and storage. Irradiation, decay and counting parameters were optimized to obtain the best sensitivity, accuracy and precision analysis. The Zn and Se concentrations were determined from the peak area of gamma-rays of 1115 and 265 KeV respectively. The analytical methodology used was validated with standard reference materials. The procedure used for the analysis, including the phases of collection, treatment of the samples and analytical determination was considered suitable for the study of trace elements in biological samples, especially plasma. (author). Dissertation to obtain the title of Bachelor in Chemistry; 46 refs., 12 figs., 17 tabs. [Espanol] Con el proposito de evaluar los efectos que se producen sobre la funcion tiroidea cuando se induce un deficiencia simple o multiple de zinc, selenio y yodo, se llevo a cabo una investigacion en animales de experimentacion. Se aplico la tecnica de analises por activacion neutronica instrumental para la determinacion de Se y Zn en plasma de ratas. Se utilizo un laboratorio limpio clase 100 para la preparacion de las muestras y se emplearon materiales de alta pureza para su recoleccion y almacenamiento. Se optimizaron los parametros de irradiacion, decaimiento y conteo de las muestras con el proposito de alcanzar la mejor sensibilidad, exactitud y precision analitica. Las concentracion de Se y Zn fueron determinadas evaluando las areas de los fotopicos de 265 y 1115 KeV respectivamente. El metodo analitico fue validado utilizando materiales de referencia. El procedimiento utilizado para el analisis

  6. Transmutation doping and recoil effects in semiconductors exposed to thermal neutrons; Transmutations provoquees et effets de recul dans les semi-conducteurs exposes aux neutrons thermiques; Prisadka i sdacha v rezul'tate prevrashcheniya poluprovodnikov pod dejstviem teplovykh nejtronov; Impurificacion por transmutacion y efectos de retroceso en los semiconductores expuestos a neutrones termicos

    Energy Technology Data Exchange (ETDEWEB)

    Crawford, Jr, J H; Cleland, J W [Solid State Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1962-01-15

    ) (gallium-71) pour chaque (arsenic-75 et selenium-77) ; en choisissant la dose d'exposition, on peut ramener la concentration electronique d'un germanium de type n a de tres faibles valeurs ou meme le transformer en un germanium de type p. La periode du gallium-71 est assez longue pour qu'il soit possible de suivre les details du par le coefficient de Hall et sa conductivite. Les experiences montrent aussi qu'environ un electron par neutron capture est elimine par des defauts de reseau crees par des noyaux de recul dont le deplacement resulte de l'emission de rayons gamma de capture. On peut rendre a ces atomes deplaces leur place normale dans le reseau en procedant a un recuit a environ 450 Degree-Sign C. D'autre part, les auteurs ont observe des effets de recul dans le silicium, deux porteurs de charge environ etant elimines a chaque capture. Ils examinent les consequences de ces resultats et des effets sur le germanium en ce qui concerne le spectre de rayons gamma de capture. Dans l'antimoniure d'indium, les rayons gamma emanant de l'indium-115 sont insuffisants pour deplacer un grand nombre de noyaux et l'effet principal est la production d'atomes d'etain-116, qui sont des lorsqu'ils remplacent des atomes d'indium. Les transmutations nucleaires provoquees ouvrent une voie nouvelle aux recherches sur de nombreux semi-conducteurs composes dans lesquels il est difficile d'introduire des impuretes par des moyens chimiques. (author) [Spanish] Los autores han estudiado muy extensamente la exposicion del germanio a neutrones termicos. Tres de los cinco isotopos de ese elemente se transmutan en impurezas quimicas; los rendimientos en atomos por 100 capturas neutronicas, y los periodos de semidesintegracion respectivos, son los siguientes: {sup 71}Ga - 30,4 - 11,4 dias; {sup 75}As - 9,8 - 82 minutos; {sup 77}Se - 1,2 - 39 horas. Por lo tanto, por cada donor ({sup 75}As y {sup 77}Se) se introducen aproximadamente tres aceptores

  7. Evaluation of area monitor response for neutrons in radiation field generated by a 15 MV clinic accelerator; Avaliacao da resposta dos monitores de area para neutrons em campo de radiacao gerado por um acelerador clinico de 15 MV

    Energy Technology Data Exchange (ETDEWEB)

    Salgado, Ana Paula

    2011-07-01

    The clinical importance and usage of linear accelerators in cancer treatment increased significantly in the last years. Coupled with this growth came the concern about the use of accelerators with energies over to 10 MeV which produce therapeutic beam contaminated with neutrons generated when high-energy photons interact with high-atomic-number materials such as tungsten and lead present in the accelerator itself. At these facilities, measurements of the ambient dose equivalent for neutrons present difficulties owing to the existence of a mixed radiation field and possible electromagnetic interference near the accelerator. The Neutron Laboratory of the IRD - Brazilian Institute for Radioprotection and Dosimetry, aiming to evaluate the survey meters performance at these facilities, initiated studies of instrumentation response in the presence of different neutron spectra. Neutrons sources with average energies ranging from 0.55 to 4.2 MeV, four different survey meters and one ionization chamber to obtain the ratio between the dose due to neutrons and gamma radiation were used in this work. The evaluation of these measurements, performed in a 15 MV linear accelerator room is presented. This work presents results that demonstrate the complexity and care needed to make neutrons measurements in radiotherapy treatment rooms containing high energy clinical accelerators. (author)

  8. Liquid radioactive wastes characterizing obtained of {sup 99} Mo production by fission; Caracterizacion de residuos liquidos radiactivos provenientes de la produccion de {sup 99} Mo por fision

    Energy Technology Data Exchange (ETDEWEB)

    Devida, Claudio; Bouza, Edgardo; Gil, Daniel; Neuringer, Silvia [Comision Nacional de Energia Atomica, Buenso Aires (Argentina). Centro Atomico Ezeiza. Unidad de Actividad Materiales y Combustibles Nucleares; Ramallo, Telma [Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Centro Atomico Ezeiza. Unidad de Actividad gestion de Residuos Radiactivos

    1999-11-01

    Among its facilities, the National Atomic Energy Commission of Argentina has a {sup 99} Mo by Fission Production Plant, which generates, among others, low and medium activity liquid waste. The characterization of the waste aims at obtaining the array of data that is necessary to carry out the processed which lead to obtain an acceptable product for its storage and final disposal. The Analytical Chemistry Laboratory faced the development, adjustment and execution of the necessary analytical procedures to achieve the physico-chemical characterization of the main liquid waste. Given the complexity and activity of the waste, high sensitivity instrumental analytical techniques were chose and the equipment was adapted to work in radiochemical hoods. In a first stage, simulated solutions were used in order to adjust the methods and techniques and to carry out studies about interference and results statistics. Afterwards, physico-chemical analysis were performed on real waste samples yielding satisfactory results as regards precision required for this kind of waste. (author) 6 refs., 4 figs., 5 tabs.

  9. Treatment of solutions of fission products - Separation of caesium-137; Traitement des solutions de produits de fission - Separation du cesium-137; Obrabotka rastvorov produktov deleniya - Razdelenie tseziya-137; Tratamiento de soluciones de productos de fision - Separacion del cesio-137

    Energy Technology Data Exchange (ETDEWEB)

    Stiennon-Bovy, R [Centre d' Etude de l' Energie Nucleaire, Mol (Belgium); Gvion, R [Commission Israelienne de l' Energie Atomique, Tel-Aviv (Israel)

    1962-01-15

    appreciable de l'activite du cesium, sa realisation a la temperature ordinaire, et la possibilite d'exploitation en regime continu. Par ce procede, la recuperation du cesium peut etre faite avant l'elimination de certains produits de fission. (author) [Spanish] Los autores han adaptado el metodo analitico de determinacion del cesio por medio de la dipierilamina a la recuperacion en escala industrial del cesio-137 contenido en soluciones de productos de fision de elevada actividad. El procedimiento propuesto permite aislar el cesio en forma de cloruro en una sola operacion y recuperar el reactivo de precipitacion con facilidad. Los autores proponen un procedimiento basico. Han estudiado el efecto de las radiaciones sobre la dipierilamina y sus compuestos. Este efecto es practicamente nulo para los compuestos solidos, y despreciable para las soluciones. Ademas, los autores han estudiado el arrastre del cesio por el ion amonico. El procedimiento descrito presenta las ventajas siguientes: elevado grado de descontaminacion del cesio, sencillez del procedimiento y facilidad con que se puede recuperar y volver a emplear el reactivo, elevado rendimiento en la recuperacion del cesio y de la dipierilamina, concentracion apreciable de la actividad del cesio, posibilidad de trabajar a temperatura ambiente, posibilidad de trabajar en regimen continuo. Este procedimiento permite recuperar cesio antes de eliminar ciertos productos de fision. (author) [Russian] Dlya promyshlennogo izvlecheniya tseziya-137 iz rastvorov produktov deleniya avtory primenili analiticheskij sposob dozirovki tseziya pri pomoshchi dipikrilamina v promyshlennom masshtabe i s vysokimi aktivnostyami. Predlagaemyj sposob pozvolyaet odnoj operatsiej izolirovat' tsezij v vide khloristogo soedineniya i legko izvlech' reagent osadka. Avtory predlagayut printsipial'nuyu skhemu. Oni izuchili dejstvie izluchenij na dipikrilamin i ego soedineniya. EHto dejstvie okazyvaetsya prakticheski ravnym nulyu dlya tverdykh soedinenij i

  10. Theory of Pulsed Neutron Experiments in Highly Heterogeneous Multiplying Media; Theorie des Experiences au Moyen des Neutrons Pulses, dans les Milieux Multiplicateurs Tres Heterogenes; O teorii ehksperimentov s impul'snymi neitronami v geterogennykh razmnozhayushchikh sredakh; Aspectos Teoricos de los Experimentos con Neutrones Pulsados en Medios Multiplicadores Muy Heterogeneos

    Energy Technology Data Exchange (ETDEWEB)

    Corno, S. E. [Instituto di Fisica ' ' A. Volta' ' (Italy); Unversity of Pavia, Pavia (Italy); SNAM, Milan [Italy

    1965-10-15

    de matiere fissile ayant une forme lineaire. La source de neutrons puises est supposee etre placee sur l'unfe des bases du cylindre. L'etendue de la zone de matiere fissile permet a l'auteur de la traiter comme s'il s'agissait d'une zone singuliere d'absorption et de multiplication dans le champ de neutrons. Comme il concentre son attention principalement sur les variations du flux de neutrons en fonction du lieu et du temps, il adopte des approximations assez grossieres pour ce qui est des variations de la population de neutrons en fonction de l'energie. Dans les limites de la theorie diffusion-age, il se peut que la reponse du dispositif a une excitation neutronique quelconque soit obtenue sous forme fermee. Avec une source modulee sinusoidalement de frequence donnee, on peut aisement montrer que, si la zone axiale singuliere est purement absorbante, le dephasage, la longueur d'onde et la constante d'attenuation des ondes neutroniques propagees le long du cylindre dependent des proprietes absoibantes de cette zone. Cet etat de choses se complique de plus en plus lorsqu'une multiplication des neutrons se produit. Dans ce cas general, la solution a laquelle l'auteur aboutit se revele evidemment etre dependante des proprietes d'absorption et de multiplication de la zone singuliere, ce qui peut donner, entre autres, l'idee d'utiliser un dispositif du modele decrit ci-dessus pour soumettre a des essais les elements de combustible des reacteurs heterogenes. (author) [Spanish] El autor ha investigado la variacion del flujo neutronico en funcion del tiempo y del espacio en un conjunto muy heterogeneo en el que se inyectan neutrones pulsados o de modulacion sinusoidal. Para mayor sencillez se opera con una instalacion formada por un bloque cilindrico de moderador pesado, en cuyo eje se encuentra una region lineal de material fisionable. La fuente neutronica se supone situada en una de las caras del cilindro. Gracias a sus dimensiones, la region fisionable puede considerarse

  11. Spectra and neutron dose of an 18 MV Linac using two geometric models of the head; Espectros y dosis por neutrones de un Linac de 18 MV usando dos modelos geometricos del cabezal

    Energy Technology Data Exchange (ETDEWEB)

    Barrera, M. T.; Pino, F.; Barros, H.; Sajo-Bohus, L. [Universidad Simon Bolivar, Laboratorio de Fisica Nuclear, Sartenejas, Baruta 1080-A, Caracas (Venezuela, Bolivarian Republic of); Davila, J. [Fisica Medica C. A., Av. Francisco de Miranda s/n, Los Palos Grandes, 1060 Miranda (Venezuela, Bolivarian Republic of); Salcedo, E. [Centro Medico Docente La Trinidad, Av. de El Haltillo, Caracas (Venezuela, Bolivarian Republic of); Vega C, H. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas, Zac. (Mexico); Benites R, J. L., E-mail: mariate9590@gmail.com [Centro de Cancerologia de Nayarit, Servicio de Seguridad Radiologica, Calz. de la Cruz 118 Sur, 63000 Tepic, Nayarit (Mexico)

    2015-10-15

    Full text: Using the Monte Carlo method, by MCNP5 code, simulations were performed with different source terms and 2 geometric models of the head to obtain spectra in energy, flow and doses of photo-neutrons at different positions on the stretcher and in the radiotherapy room. The simplest model was a spherical shell of tungsten; the second was the complete model of a heterogeneous head of an accelerator Varian ix. In both models Tosi function was used as a source term. In addition, for the second model Sheikh-Bagheri distribution was used for photons and photo-neutrons were generated. Also in both models the radiotherapy room of Gurve group of the Teaching Medical Center La Trinidad was included, which is equipped with an accelerator Varian Clinic 2100. In this Center passive detectors PADC (Cr-39) were irradiated with neutron converters, with 18 MeV photons radiation. The measured neutron flow was compared with that obtained with Monte Carlo calculations. The Monte Carlo flows are similar to those measured at the isocenter. The simplest model underestimates the neutron flow compared with the calculated flows with the heterogeneous model of the head. (Author)

  12. Tratamiento del cáncer por captura neutrónica de boro: Su aplicación al carcinoma indiferenciado de tiroides Boron neutron capture therapy applied to undifferentiated thyroid carcinoma

    Directory of Open Access Journals (Sweden)

    Mario A. Pisarev

    2006-12-01

    Full Text Available El cáncer indiferenciado de tiroides es un tumor muy agresivo, de muy mal pronóstico y sin tratamiento efectivo. La terapia por captura neutrónica de boro (BNCT podría ser una alternativa para el tratamiento de esta enfermedad. Se basa en la captación selectiva de boro por el tumor y su activación por un haz de neutrones. El boro activado libera un núcleo de litio-7 y una partícula alfa, las cuales tienen una alta transmisión linear de energía (linear energy transfer, LET y un alcance de 5-9 µm, destruyendo el tumor. En estudios previos hemos mostrado que la línea celular humana de cáncer indiferenciado de tiroides (ARO tiene una captación selectiva de borofenilalanina (10BPA tanto in vitro como después de ser implantada en ratones NIH nude. También demostramos en estos animales inyectados con BPA e irradiados con un haz de neutrones térmicos, un 100% de control sobre el crecimiento tumoral y un 50% de cura histológica. En trabajos posteriores mostramos que la porfirina 10BOPP tetrakis-carborane carboxylate ester de 2,4-bis-(a,b-dihydroxyethyl-deutero-porphyrin IX cuando es inyectada 5-7 días antes que el BPA se obtiene una concentración tumoral de boro de aproximadamente el doble que el BPA solo (45-38 ppm vs. 20 ppm. La posterior irradiación con neutrones mostró un 100% de remisión completa en animales con tumores cuyo volumen pre-tratamiento era de 50 mm³ o menor. Los perros padecen CIT espontáneo, con un comportamiento biológico similar al humano, y una captación selectiva de BPA, abriendo la posibilidad de su tratamiento por BNCT.Undifferentiated thyroid carcinoma (UTC is an aggressive tumor with a poor prognosis due to the lack of an effective treatment. Boron neutron capture therapy (BNCT is based on the selective uptake of boron by the tumor and its activation by a neutron beam, releasing lithium-7 and an alpha particle that will kill the tumor cells by their high linear energy transfer (LET. In previous

  13. Diffusion Parameters of BeO by the Pulsed Neutron Method; Calcul des Parametres de Diffusion de BeO par la Methode des Neutrons Pulses; Opredelenie diffuzionnykh parametrov BeO s pomoshch'yu metoda impul'snykh nejtronov; Determinacion de los Parametros de Difusion en el BeO por el Metodo de los Neutrones Pulsados

    Energy Technology Data Exchange (ETDEWEB)

    Joshi, B. V.; Nargundkar, V. R.; Subbarao, K. [Atomic Energy Establishment Trombay, Bombay (India)

    1965-08-15

    la position et la longueur du compteur d'une part, la position de la source d'autre part, il est possible d'eliminer la plupart des harmoniques spatiaux. Il est egalement possible de tenir compte de n'importe quel bruit de fond constant pour le calcul de la constante de decroissance. Il faut eviter les laplaciens tres eleves afin de ne pas avoir d {sup h}armoniques du temps. Tous les harmoniques qui restent sont rendus inoperants par un retard en temps adequat. Les auteurs ont determine la constante de decroissance du mode fondamental de la population de neutrons thermiques pour plusieurs laplaciens. Ils discutent les conditions a remplir pour une determination exacte de la constante du refroidissement par diffusion C. Pour la glucine, ils ont obtenu les constantes suivantes: {lambda}{sub 0} (constante d'absorption) = 156, 02 {+-} 4, 37 s{sup -1}. D (coefficient dediffusion) = (1,3334 {+-} 0,0128) * 10{sup 5} cm{sup 2}/s, C (constante du refroidissement de diffusion) = (-4,8758 {+-} 0,5846) * 10{sup 5} cm{sup 4}/s. Les auteurs ont etudie le role que peut jouer, dans la determination des parametres de diffusion, le fait que la contribution du terme en B{sup 6} est neglige; ils montrent qu'il est considerable. Ce serait la probablement la cause des ecarts entre les valeurs de C obtenues pour un meme ralentisseur par differents chercheurs. (author) [Spanish] Los autores describen el empleo del metodo de los neutrones pulsados para determinar con precision los parametros de difusion en moderadores. Con ayuda de este metodo, han obtenido los parametros de difusion en el BeO. Las rafagas de neutrones se generaron mediante un acelerador en cascada pulsando la fuente ionica y empleando la reaccion Be (d, n). Como detector se utilizo un contador proporcional de BF{sub 3} enriquecido. Los autores demuestran que por seleccion adecuada de la posicion y longitud del contador y de la ubicacion de la fuente, pueden eliminarse la mayoria de los armonicos espaciales. En el calculo de

  14. Estimate of the damage in organs induced by neutrons in three-dimensional conformal radiotherapy; Estimacion del dano en organos inducido por neutrones en radioterapia conformada en 3D

    Energy Technology Data Exchange (ETDEWEB)

    Benites R, J. L. [Centro Estatal de Cancerologia de Nayarit, Servicio de Seguridad Radiologica, Calzada de la Cruz 118 sur, 63000 Tepic, Nayarit (Mexico); Vega C, H. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas (Mexico); Uribe, M. del R., E-mail: jlbenitesr@prodigy.net.mx [Instituto Tecnico Superior de Radiologia, Calle Leon No. 129, 63000 Tepic, Nayarit (Mexico)

    2014-08-15

    By means of Monte Carlo methods was considered the damage in the organs, induced by neutrons, of patients with cancer that receive treatment in modality of three-dimensional conformal radiotherapy (3D-CRT) with lineal accelerator Varian Ix. The objective of this work was to estimate the damage probability in radiotherapy patients, starting from the effective dose by neutrons in the organs and tissues out of the treatment region. For that a three-dimensional mannequin of equivalent tissue of 30 x 100 x 30 cm{sup 3} was modeled and spherical cells were distributed to estimate the Kerma in equivalent tissue and the absorbed dose by neutrons. With the absorbed dose the effective dose was calculated using the weighting factors for the organ type and radiation type. With the effective dose and the damage factors, considered in the ICRP 103, was considered the probability of damage induction in organs. (Author)

  15. Determination of nitrogen in wheat flour through Activation analysis using Fast neutron flux of a Thermal nuclear reactor; Determinacion de nitrogeno en harina de trigo mediante analisis por activacion empleando el flujo de neutrones rapidos de un reactor nuclear termico

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez G, T

    1976-07-01

    In this work is done a technical study for determining Nitrogen (protein) and other elements in wheat flour Activation analysis, with Fast neutrons from a Thermal nuclear reactor. Initially it is given an introduction about the basic principles of the methods of analysis. Equipment used in Activation analysis and a brief description of the neutron source (Thermal nuclear reactor). The realized experiments for determining the flux form in the irradiation site, the half life of N-13 and the interferences due to the sample composition are included too. Finally, the obtained results by Activation and the Kjeldahl method are tabulated. (Author)

  16. Thermal Neutron Spectral and Spatial Distributions in Light-Water-Moderated Uranium Lattices; Distributions Spectrale et Spatiale des Neutrons Thermiques dans des Reseaux a Uranium et a Eau Leger; Spektral'noe i prostranstvennoe raspredelenie teplovykh nejtronov v uranovykh reshetkakh s vodnym zamedlitelem; Distribuciones Espectral y Espacial de los Neutrones Termicos en los Reticulados de Uranio Moderados por Agua Ligera

    Energy Technology Data Exchange (ETDEWEB)

    Hardy, J.; Volpe, J. J.; Klein, D.; Schmidt, E.; Gelbard, E. [Bettis Atomic Power Laboratory, Pittsburgh, PA (United States)

    1964-02-15

    realizados acerca del comportamiento de los neutrones termicos en los reticulados de uranio moderados por agua ligera. Los experimentos pertenecen a dos tipos principales: mediciones del grado de utilizacion termica y mediciones, por activacion, de la distribucion espacial de los neutrones termicos en un medio acuoso uniformemente envenenado. Esos experimentos se concibieron con miras a comprobar la validez de los actuales modelos teoricos, distinguiendo los efectos espectrales de los espaciales en el interior de un reactor. Se han efectuado eomparaciones con modelos teoricos que entraflan distintas aproximaciones relacionadas con la teoria del transporte y el nucleo de dispercion de los neutrones termicos. La primera serie de experimentos consistio en medir por el procedimiento de activacion los factores de desventaja termica en distintas celdas de reticulados del conjunto TRX, que constituye un reactor de uranio ligeramente enriquecido, moderado por H{sub 2}O, con barras de combustible cilindricas dispuestas en haces hexagonales. Los autores han comparado los resultados de las mediciones del grado de utilizacion termica con los datos de calculos efectuados con arreglo al metodo de Montecarlo. Utilizaron dos nucleos, el de Radkowsky y el de N elk in. El nucleo de Radkowsky constituye una aproximacion de primer orden que se viene utilizando umversalmente en el disello de los reactores. El nucleo de Nelkin, por su parte, representa una descripcion mas reciente y mas detallada del nucleo de dispersion. Dado que los indices de absorcion calculados para los neutrones termicos dependen de la eleccion del nucleo de dispersion, especialmente si el espectro del flujo neutronico no es maxwelliano, se ideo otra serie de experimentos de activacion con ayuda del conjunto TRX para verificar de un modo mas directo la utilidad del nucleo de dispersion. Los experimentos se realizaron en condiciones tales que la deformacion espectral se debia esencialmente a un envenenamiento uniforme. Las

  17. The Technology and Applications of Large Fission Product Beta Sources; Technologie et applications des grandes sources beta de fission; Tekhnologiya i primenenie krupnykh istochnikov beta-izluchenij, ispuskaemykh produktami deleniya; Tecnologia y utilizacion de los productos de fision como fuentes de irradiacion beta de elevada intensidad

    Energy Technology Data Exchange (ETDEWEB)

    Silverman, Joseph [Radiation Applications Incorporated (United States)

    1960-07-15

    incluso puede ser nociva. Existen otros dos campos en los cuales no conviene emplear electrones artificialmente acelerados; las sintesis quimicas radioinducidas que se lleven a cabo en recipientes a presion y varios tipos de reacciones en cadena inducidas por radicales libres cuyo indice de produccion por kilowatio disminuye en funcion de la raiz cuadrada de la intensidad de la dosis. Las fuentes beta de gran extension presentan sin duda ventajas en todas estas operaciones y, como pueden obtenerse con buen rendimiento en los procesos de fision, merecen un nuevo y detenido examen. Basandose en estas consideraciones , el autor efectuo un estudio, patrocinado por la Comision de Energia Atomica de los Estados Unidos, sobre las aplicaciones y la tecnologia de los productos de fision como fuentes de irradiacion beta. Los resultados obtenidos fueron los siguientes: 1. Existen posibilidades de aplicacion comercial de los productos de fision como emisores beta en los tratamientos por irradiacion, especialmente para la modificacion por copolimerizacio n de injerto de la superficie de los materiales plasticos moldeados y de las fibras sinteticas. 2. Perfeccionando convenientement e las tecnicas existentes, pueden fabricarse fuentes beta potentes, resistentes, inertes, seguras y economicas. Los productos de fision incorporados en vidrio parecen ser las mas prometedoras. 3. Los calculos de la absorcion de particulas beta indican que pueden di- senarse fuentes de gran extension cuyo rendimiento alcance al 20 por ciento. El autor ha formulado ecuaciones y ha trazado curvas que indican la variacion de las dosis del rendimiento beta en funcion de las relaciones geometricas y de la composicion de varios sistemas fuente-blanco. Se esta llevando a cabo un programa de experiencias para comprobar la validez de estos calculos. 4. El analisis de los costos indica que, en el plano economico, los productos de fision pueden competir como emisores beta con otras fuentes de radiacion. (author

  18. Origin identification for Cantona, Puebla, obsidians by the analysis method of neutron activation (NAA); Identificacion de procedencia para obsidianas de Cantona, Puebla, por el metodo de analisis por activacion neutronica (AAN)

    Energy Technology Data Exchange (ETDEWEB)

    Tellez N, A. L.

    2013-07-01

    There are tests that most of the obsidian worked in the workshops of Cantona, Puebla, is coming from the mineral deposits of Oyameles-Zaragoza, but also has been detected obsidian that macroscopically belongs to other mineral deposits. The present work has as purpose to determine the provenance of an obsidian sample obtained in the Cantona Site to know if there was the presence of obsidian of other mineral deposits. For the study the neutron activation analysis was used to identify the presence of other deposits. An explanation on the treatment to the selected pieces is included, the preparation of the same ones for its irradiation in the nuclear reactor, the counting and statistical study of the results. Finally the results of the selected samples are presented, indicating their origin places, that time comes and the interpretation of the results is given. (Author)

  19. Determination of rare earth and uranium in reference biological materials certified by the method of neutron activation analysis; Determinacao de terras raras e de uranio em materiais biologicos de referencia certificados pelo metodo de analise por ativacao com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Lais H.P.; Saiki, Mitiko, E-mail: laispaciulli@gmail.com, E-mail: mitiko@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    The objective of this study was to evaluate the precision and accuracy of the determinations of Sc, La, Ce, Nd, Sm, Eu, Tb, Yb, Lu and U in certified reference materials (CRMs). To solve the problem of interference from fission products of U in the determination of lanthanides were obtained correction factors for this interference for {sup 140}La, {sup 141}Ce, {sup 143}Ce, {sup 153}Sm and {sup 147}Nd. The experimental procedure of Neutron Activation Analysis consisted of irradiating aliquots of each of the CRMs with synthetic standards of elements under thermal neutron flux of the IEA-R1 nuclear reactor, followed by gamma-ray spectrometry using a high-resolution hyperpurity GE detector. The analyzes of CRMs indicate good accuracy and precision of results, demonstrating the feasibility of applying of established procedure in NAA of elements studied in organic vegetable matrices.

  20. Neutron Skyshine in shielding projects of radiotherapy: comparison between theoretical approach and simulation by Monte Carlo method; 'Skyshine' de neutrons em projetos de blindagens de radioterapia: comparacao entre abordagem teorica e simulacao por metodo de Monte Carlo

    Energy Technology Data Exchange (ETDEWEB)

    Falcao, R.C.; Facure, A. [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Santini, E.S. [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Centro Brasileiro de Pesquisas Fisicas (CBPF), Rio de Janeiro, RJ (Brazil); Silva, A.X. [Coordenacao dos Programas de Pos-Graduacao de Engenharia (PEN/COPPE/UFRJ), RJ (Brazil). Programa de Engenharia Nuclear

    2005-07-01

    In this work, the MCNP code is used to simulate the transport of neutrons in a room of radiotherapy, whose shieldings are designed according to the method of skyshine (scattering in the atmosphere). The simulations are compared with the results obtained from empirically established expressions, which are normally used for designing the ceilings of the rooms facilities, ensuring that dose rates (neutrons + photons) around them do not exceed the maximum limits allowed by the standards of the CNEN. Good agreement is observed between the doses calculated according to these expressions and those obtained through simulation by Monte Carlo in the case of rooms without ceiling, and an overestimate of the calculations by a factor 2 or 3 in relation to the simulations, in the case of rooms with ceiling.

  1. Fission track thermochronology of Neogene plutons in the Principal Andean Cordillera of central Chile (33-35°S: Implications for tectonic evolution and porphyry Cu-Mo mineralization Termocronología mediante trazas de fision de plutones neógenos en la Cordillera Principal Andina de Chile central (33-35°S: Implicancias para la evolución tectónica y mineralización de pórfidos de Cu-Mo

    Directory of Open Access Journals (Sweden)

    Víctor Maksaev

    2009-07-01

    ápido desenterramiento de los pórfidos de Cu-Mo de clase mundial de Río Blanco-Los Bronces y El Teniente. Las edades de circones por trazas de fision coinciden con datos geocronológicos 40Ar/39Ar previos a las intrusiones y con algunas de las edades de trazas de fision en apatitas, siendo coherentes con el enfriamiento rápido relacionado con procesos ígneos después de la intrusion magmática. Los datos son consistentes con un maximo de aproximadamente 8 km para la exhumación neógena de los plutones.

  2. Design of a computation tool for neutron spectrometry and dosimetry through evolutionary neural networks; Diseno de una herramienta de computo para la espectrometria y dosimetria de neutrones por medio de redes neuronales evolutivas

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz R, J. M.; Vega C, H. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Ingenieria Electrica, Av. Ramon Lopez Velarde No. 801, Col. Centro, Zacatecas (Mexico); Martinez B, M. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Av. Ramon Lopez Velarde No. 801, Col. Centro, Zacatecas (Mexico); Gallego, E. [Universidad Politecnica de Madrid, Departamento de Ingenieria Nuclear, Jose Gutierrez Abascal No. 2, E-28006 Madrid (Spain)], e-mail: morvymmyahoo@com.mx

    2009-10-15

    The neutron dosimetry is one of the most complicated tasks of radiation protection, due to it is a complex technique and highly dependent of neutron energy. One of the first devices used to perform neutron spectrometry is the system known as spectrometric system of Bonner spheres, that continuous being one of spectrometers most commonly used. This system has disadvantages such as: the components weight, the low resolution of spectrum, long and drawn out procedure for the spectra reconstruction, which require an expert user in system management, the need of use a reconstruction code as BUNKIE, SAND, etc., which are based on an iterative reconstruction algorithm and whose greatest inconvenience is that for the spectrum reconstruction, are needed to provide to system and initial spectrum as close as possible to the desired spectrum get. Consequently, researchers have mentioned the need to developed alternative measurement techniques to improve existing monitoring systems for workers. Among these alternative techniques have been reported several reconstruction procedures based on artificial intelligence techniques such as genetic algorithms, artificial neural networks and hybrid systems of evolutionary artificial neural networks using genetic algorithms. However, the use of these techniques in the nuclear science area is not free of problems, so it has been suggested that more research is conducted in such a way as to solve these disadvantages. Because they are emerging technologies, there are no tools for the results analysis, so in this paper we present first the design of a computation tool that allow to analyze the neutron spectra and equivalent doses, obtained through the hybrid technology of neural networks and genetic algorithms. This tool provides an user graphical environment, friendly, intuitive and easy of operate. The speed of program operation is high, executing the analysis in a few seconds, so it may storage and or print the obtained information for

  3. Multi-element analysis of wheat flour and white bread by neutron activation.; Analisis multielemental en harina de trigo y pan blanco por activacion neutronica.

    Energy Technology Data Exchange (ETDEWEB)

    Godinez A, M A

    1994-12-31

    One of the best source of feeding even for the human being as for animals are the Cereals. Although they are mainly energetic aliment, due to its composition in starch, they are a very important source of proteins and amino acids. They contribute mineral elements to the diet. Even those elements constitute a very small part of the total diet, they take a very important place in many human metabolic processes. To make a multielemental analysis of an aliment is very important that we are based on a very sensible analytic technique so we are able to find them, just as the Neutronic Activation. This Nuclear technique allows you to make a qualitative and quantitative analysis of the elements that are in a sample, but it does n`t show the way in which the elements are presented. It is based in turning those elements into radioactive ones through its exposition to an uniform and constant fluid of neutrons, so then its radioactivity can be determined. The present work has as a main purpose to make a multielemental analysis of the wheat flour and white bread through the Neutronic Activation Technique, using the comparator method and establishing previously the most appropriate work conditions as much irradiation as digestion and measuring of the radioactivity of the sample. In this way, it was able to know that the wheat flour has potassium, chlorine, magnesium, sodium, iron, zinc, manganese, rubidium and selenium elements in a concentration of 2000, 700, 500, 25, 18, 13, 5.5, 0.9 and 0.01 - 0.3 mg/g respectively. In an other hand it was found that the white bread has the same elements than the wheat flour but its concentration was: 1700, 9000, 400, 7000, 52, 13, 6, 1 and 0.05 - 0.3 mg/g respectively. (Author).

  4. Neutron stars

    International Nuclear Information System (INIS)

    Irvine, J.M.

    1978-01-01

    The subject is covered in chapters entitled: introduction (resume of stellar evolution, gross characteristics of neutron stars); pulsars (pulsar characteristics, pulsars as neutron stars); neutron star temperatures (neutron star cooling, superfluidity and superconductivity in neutron stars); the exterior of neutron stars (the magnetosphere, the neutron star 'atmosphere', pulses); neutron star structure; neutron star equations of state. (U.K.)

  5. Estimation of damage by inmates of a PWR Reactor neutron irradiation. Project ZIRP; Estimacion del Dano por Irradiacion Neutronica en los Internos de un Reactor PWR. Proyecto ZIRP

    Energy Technology Data Exchange (ETDEWEB)

    Cadenas Mendicoa, A. M.

    2013-07-01

    The study presented here focuses on the analysis of neutron and gamma irradiation damage suffered by the inmates of the JC NPP reactor metallic materials throughout its operational life. Such analysis of radiation are part of a project of great international impact, led by EPRI (Electric Power Research Institute) from the MRP (Materials Reliability Program), which aims to relate the degradation of the properties of metallic materials of the inmates of the reactor, with the conditions of operation and irradiation to which have been subjected during the operational life of the plant.

  6. Characterization of the volcanic eruption emissions using neutron activation analysis; Caracterizacion de las emisiones de una erupcion volcanica mediante analisis por activacion neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Pla, Rita R. [Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Radioquimica, Tecnicas Analiticas Nucleares; Tafuri, Victoria V. [Servicio Meteorologico Nacional, Buenos Aires (Argentina). Centro de Contaminacion del Aire

    1997-10-01

    Characterization of the volcanic particulate material has been performed by analyzing aerosols and ashes with instrumental neutron activation analysis. Crustal enrichment factors were calculated using the elemental concentration and clustering techniques, and multivariate analysis were done. The analytical and data treatment methodologies allowed the sample differentiation from their geographical origin viewpoint, based on their chemical composition patterns, which are related to the deposit formation processes, which consist of direct deposition from the volcanic cloud, and removal by wind action after the end of the eruption, and and finally the deposition. (author). 8 refs., 5 figs.

  7. Carcinogenesis by Fast Neutrons Relative to X-Rays in Mice; Carcinogenese chez les Souris sous l'Effet des Neutrons Rapides et des Rayons X; Sravnitel'naya chastota vozniknoveniya rakovykh opukholej u myshej pri obluchenii bystrymi nejtronami i rentgenovskimi luchami; Accion Carcinogenica Comparada de los Neutrones Rapidos y de los Rayos X en el Raton

    Energy Technology Data Exchange (ETDEWEB)

    Cole, L. J.; Nowell, P. C. [Division of Biological and Medical Sciences, U.S. Naval Radiological Defense Laboratory, San Francisco, CA (United States); Department of Pathology, School of Medicine, University of Pennsylvania, Philadelphia, PA (United States)

    1964-05-15

    a una dosis unica (500 rad) de rayos X de 250 kVp. En los ratones irradiados y sometidos a nefrectomia unilateral (Grupo IV), la frecuencia de neoplasmas renales se aproximo al 100%, mientras que en los animales testigo dichas lesiones fueron poco frecuentes. Los autores estudian la induccion de estos neoplasmas en lo que respecta a su iniciacion neutronica y su agravacion mediante el uso de determinados agentes estimulantes de la proliferacion. De los datos se desprende que, por lo que se refiere a la iniciacion de neoplasmas renales en el raton, los neutrones de fision son dos veces mas eficaces que los rayos X de 250 kVp. En cuanto a la formacion de linfomas en la misma variedad de ratones, la frecuencia en los sujetos irradiados con neutrones (11%) es menor que en los expuestos a los rayos X (29%). (author) [Russian] Mo lodye vzroslye myshi linii LAF podvergalis' oblucheniju odnokratnoj subletal'noj dozoj nejtronov spektra delenija i raspredeljalis' sledujushhim obr azom: gruppa 1-195 do 199 rad, zhivotnye poluchali mesjac spustja odnokratno podkozhno in'ekciju CCl{sub 4} : gruppa I I -CCl{sub 4} vvodilsja za den' do nejtronnogo obluchenija (280-329 rad); gruppa III -to l'k o CCl{sub 4} be z obluchenija; gruppa I V -odnostoronnee udalenie pochek, osushhestvlennoe za den' do nejtronnogo obluchenija (320 - 328 rad); gruppa V -to l'ko nejtronnoe obluchenie (200-320 rad). V gruppe I u 75% myshej, ubityh cherez 12 - 16 mesjacev posle obluchenija, obnaruzheny gepatomy v to vremja, kak u myshej vtoroj gruppy gepatomy obnaruzheny u 92%. Naprotiv, opuhol' pecheni pojavilas' u 14% myshej, podvergnutyh tol'ko nejtronnomu oblucheniju (gruppa V) i u 2,4% myshej, podvergnutyh odnokratnomu rentgenovskomu oblucheniju (500 rad) s pikovym naprjazheniem 250 kv. Chastota pojavlenija opuholej pochek priblizhalas' k 100% u obluchennyh myshej s odnostoronnej nefrjektamiej (gruppa IV ) , v to vremja kak takie porazhenija u kontrol'nyh myshej byli redkimi. Obsuzhdaetsja inducirovanie

  8. Determination of uranium fission products interference factors in neutron activation analysis; Determinacao de fatores de interferencia de produtos de fissao de uranio na analise por ativacao neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Ribeiro Junior, Ibere Souza

    2014-09-01

    Neutron activation analysis is a method used in the determination of several elements in different kinds of matrices. However, when the sample contains high U levels the problem of {sup 235}U fission interference occurs. A way to solve this problem is to perform the correction using the interference factor due to U fission for the radionuclides used on elemental analysis. In this study was determined the interference factor due to U fission for the radioisotopes {sup 141}Ce, {sup 143}Ce, {sup 140}La, {sup 99}Mo, {sup 147}Nd, {sup 153}Sm and {sup 95}Zr in the research nuclear reactor IEA-R1 on IPEN-CNEN/SP. These interference factors were determined experimentally, by irradiation of synthetic standards for 8 hours in a selected position in the reactor, and theoretically, determining the epithermal to neutron fluxes ratio in the same position where synthetic standards were irradiated and using reported nuclear parameters on the literature. The obtained interference factors were compared with values reported by other works. To evaluate the reliability of these factors they were applied in the analysis of studied elements in the certified reference materials NIST 8704 Buffalo River Sediment, IRMM BCR- 667 Estuarine Sediment e IAEA-SL-1 Lake Sediment. (author)

  9. Sistema de adquisición y transmisión de datos, por fibra óptica, para un generador de neutrones.

    Directory of Open Access Journals (Sweden)

    Sergio Vergara Limon

    2010-11-01

    Full Text Available Normal 0 21 false false false MicrosoftInternetExplorer4 st1:*{behavior:url(#ieooui } /* Style Definitions */ table.MsoNormalTable {mso-style-name:"Tabla normal"; mso-tstyle-rowband-size:0; mso-tstyle-colband-size:0; mso-style-noshow:yes; mso-style-parent:""; mso-padding-alt:0cm 5.4pt 0cm 5.4pt; mso-para-margin:0cm; mso-para-margin-bottom:.0001pt; mso-pagination:widow-orphan; font-size:10.0pt; font-family:"Times New Roman"; mso-ansi-language:#0400; mso-fareast-language:#0400; mso-bidi-language:#0400;} Se presenta el desarrollo construcción   y aplicación de un sistema virtual de adquisición de datos basado en el uso de microcontroladores, fibra óptica y PC; que restablece la comunicación entre los módulos básicos que componen un Generador de Neutrones. Se muestra como queda modernizada la interfaz original del generador, al automatizarse la adquisición de datos sobre sus parámetros de explotación.  Se introduce el uso de la PC en el Generador de Neutrones y se establece el antecedente para extender la automatización a otros subsistemas de la instalación.  

  10. 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

    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

  11. Contents evaluation of some essential and toxic elements in children and elders diet by neutron activation analysis; Avaliacao do conteudo de alguns elementos essenciais e toxicos em dietas de criancas e idosos pelo metodo de analise por ativacao com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Maihara, Vera Akiko

    1996-12-31

    Essential and toxic elements in the 19 diet samples from pre-school children and 23 diet samples from elderly people, have been determined by neutron activation analysis. The diet samples were collected by duplicate portion method. A radiochemical separation procedure was developed and applied for determining Cd, Co, Cr, Fe, Mo, Sb, U, Th, W and Zn, based on retention of these elements in a Chelex-100 resin. In the case of As and Se, the procedure was based on retention in inorganic exchanger TDO (tin dioxide). The contents of proteins, lipids and carbohydrates were also analysed. The results have been presented and discussed 135 refs., 29 figs., 36 tabs.

  12. Determination of phosphorus and calcium in biological samples by activation with 14 MeV neutrons; Determinacao de fosforo e calcio em amostras biologicas por ativacao com neutrons de 14 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Berretta, Jose Roberto

    1995-07-01

    Analytical methods for phosphorus and calcium in biological samples by means of activation with 14 MeV neutrons, using the Van de Graaff accelerator from the Instituto de Pesquisas Energeticas e Nucleares, SP, Brazil are developed. For phosphorus analysis, powder samples were pressed into pellets, weighed and transferred to polyethylene plastic envelopes. The pellets with cadmium shielding were irradiated under a fast neutron flux for 5 to 10 minutes, and further counted in a HPGe detector for 5 minutes. Calcium analysis was performed by cyclic irradiation. Samples were irradiated for 10 minutes. After a decay time of 2 minutes, gamma counting was performed for 10 minutes. After a decay time of 2 minutes, a new irradiation ws made. The irradiation cycle was repeated 5 times and the counting spectrum obtained in each cycle was accumulated in the multi channel analyser. The variation of the neutron flux was followed by using a BF{sub 3} detector calibrated with and aluminium monitor. By means of the gamma spectrum and the neutron counting of the BF{sub 3} detector it was possible to estimate phosphorus and calcium concentrations in the sample analyzed. The methods were checked in the reference samples from the International Atomic Energy Agency and in commercial samples of powder milk, fertilizer and animal bone. Phosphorus contents in bone (A3/74) and milk (A-11) reference materials were (15.6 +- 1.8%) and (0.9 +- 0.1)%, respectively. These values are in good agreement to the certified values (15.5 +- 0.5)% and (0.910 +- 0.102)%, respectively. Calcium analysis carried out in bone (A3/74) presented a value of (31.8+-4.1)% and the certified value was of (31.3 +- 0.3)%. Detection limits for phosphorus and calcium were determined in different analyzed samples. The agreement of the results obtained with the certified values confirmed the suitability of the methods for phosphorus and calcium analysis. The methods are fast and laborious chemical procedures are not required

  13. Contents evaluation of some essential and toxic elements in children and elders diet by neutron activation analysis; Avaliacao do conteudo de alguns elementos essenciais e toxicos em dietas de criancas e idosos pelo metodo de analise por ativacao com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Maihara, Vera Akiko

    1997-12-31

    Essential and toxic elements in the 19 diet samples from pre-school children and 23 diet samples from elderly people, have been determined by neutron activation analysis. The diet samples were collected by duplicate portion method. A radiochemical separation procedure was developed and applied for determining Cd, Co, Cr, Fe, Mo, Sb, U, Th, W and Zn, based on retention of these elements in a Chelex-100 resin. In the case of As and Se, the procedure was based on retention in inorganic exchanger TDO (tin dioxide). The contents of proteins, lipids and carbohydrates were also analysed. The results have been presented and discussed 135 refs., 29 figs., 36 tabs.

  14. Determination of silver, gold, zinc and copper in mineral samples by various techniques of instrumental neutron activation analysis; Determinacion de plata, oro, zinc y cobre en muestras minerales mediante diversas tecnicas de analisis por activacion de neutrones instrumental

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez R, N. I.; Rios M, C.; Pinedo V, J. L. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas, Zac. (Mexico); Yoho, M.; Landsberger, S., E-mail: neisla126@hotmail.com [University of Texas at Austin, Nuclear Engineering Teaching Laboratory, Austin 78712, Texas (United States)

    2015-09-15

    Using the method of instrumental neutron activation analysis, mineral exploration samples were analyzed in order to determine the concentrations of silver, gold, zinc and copper; these minerals being the main products of benefit of Tizapa and Cozamin mines. Samples were subjected to various techniques, where the type of radiation and counting methods were chosen based on the specific isotopic characteristics of each element. For calibration and determination of concentrations the comparator method was used, certified standards were subjected to the same conditions of irradiation and measurement that the prospecting samples. The irradiations were performed at the research reactor TRIGA Mark II of the University of Texas at Austin. The silver concentrations were determined by Cyclical Epithermal Neutron Activation Analysis. This method in combination with the transfer pneumatic system allowed a good analytical precision and accuracy in prospecting for silver, from photo peak measurement 657.7 keV of short half-life radionuclide {sup 110}Ag. For the determination of gold and zinc, Epithermal Neutron Activation Analysis was used, the photo peaks analyzed corresponded to the energies 411.8 keV of radionuclide {sup 199}Au and 438.6 keV of metastable radionuclide {sup 69m}Zn. On the other hand, copper quantification was based on the photo peak analysis of 1039.2 keV produced by the short half-life radionuclide {sup 66}Cu, by Thermal Neutron Activation Analysis. The photo peaks measurement corresponding to gold, zinc and copper was performed using a Compton suppression system, which allowed an improvement in the signal to noise relationship, so that better detection limits and low uncertainties associated with the results were obtained. Comparing elemental concentrations the highest values in silver, zinc and copper was for samples of mine Tizapa. Regarding gold values were found in the same range for both mines. To evaluate the precision and accuracy of the methods used

  15. Application of neutron activation analysis for the determination of essential elements in egg samples; Aplicacao da analise por ativacao com neutrons para a determinacao de elementos essenciais em amostras de ovos

    Energy Technology Data Exchange (ETDEWEB)

    Gomes, Bruna G.; Maihara, Vera A.; Avegliano, Roseane P., E-mail: brunagabrielegomes@gmail.com, E-mail: vmaihara@ipen.br, E-mail: pagliaro@usp.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    The eggs are among the twenty foods consumed by the population of the five major regions of Brazil. Among the types of eggs, there are differences in nutritional value, which can vary according to the food of the bird. This study evaluating the elements Cl, K, Mg, Mn and Na considered essential micronutrients in food, because they are fundamental in several metabolic processes necessary for the maintenance and training of the human body. We analyzed three types of eggs: egg whites, of the quail, and the colonial in cooked and raw form, using the Instrumental Neutron Activation Analysis method (INAA). The egg samples were lyophilized and pulverized before analysis. To validate the methodology, reference materials NIST RM 8415 Whole Egg Powder and NIST SRM 1567 Wheat Flour were analyzed. The samples, reference materials and standards of the elements were irradiated for 20 seconds under a thermal neutron flux of 6,6x10{sup 12} cm -2 s -1 in the nuclear research reactor IEA-R1 of IPEN-CNEN / SP. The results were consistent with the values of the Brazilian Table of Food Composition (TACO)

  16. Chemical characterization of diets consumed in the COSEAS restaurant, by neutron activation analysis; Caracterizacao quimica de dietas consumidas no restaurante do COSEAS/USP-SP, por ativacao neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Favaro, Deborah I.T. [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil). Lab. de Analise por Ativacao Neutronica]. E-mail: defavaro@ipen.br; Chioccola, Gabriella S.; Bortoli, Maritsa C.; Cozzolino, Silvia M.F. [Sao Paulo Univ., SP (Brazil). Faculdade de Ciencias Farmaceuticas. Lab. de Alimentos e Nutricao Experimental]. E-mail: gabich@usp.br

    2005-07-01

    This study presents the results of chemical characterization of meals (lunch) offered by COSEAS/USP-SP restaurant, during 5 non consecutive days. These meals were collected in triplicate, in the same way they are offered to the users, being freeze-dried and prepared for chemical analysis. In the total, 15 samples were collected. The proximate composition was determined by using the standard methodologies according to AOAC (1995). The contents of some micronutrients (Ca, Fe, K, Na, Se and Zn) were determined by instrumental neutron activation analysis. The methodology validation was performed by certified reference materials analyses: Oyster Tissue (NIST SRM 1566{sup b}), Orchard Leaves (NIST SRM 1541) and Peach Leaves (NIST SRM 1547). >From concentration results the daily intake of each micronutrient was calculated considering this meal as 40% of the total daily intake and the values were compared to the new dietary recommendations of micronutrients (Dietary Reference Intakes-DRIs, Institute of Medicine, USA), for the women in the life stage from 19 to 30 years. Comparing the average values found with the recommended values, it was verified that macronutrients and Fe, Se and Zn micronutrients reached the values set by new DRIs. For Ca and K the daily intake was inadequate and Na, exceeded the recommended value. (author)

  17. A study on chemical element determinations in human nails by neutron activation analysis; Estudo sobre determinacao de elementos quimicos em unhas humanas pelo metodo de analise por ativacao com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Sanches, Thalita Pinheiro

    2012-07-01

    Nail analyses have been the object of study in order to assess the levels of elements accumulated in the human organism and to use this tissue to monitor environmental and occupational exposure, to evaluate the nutritional status, to verify intoxication by toxic metals and to diagnose or to prevent diseases. Nail analyses present advantages due to easy sample collection, storage, transportation and this tissue provides element level accumulation over time. However, there is controversy regarding the application of nail analysis data due to difficulties to establish reliable reference values or element concentration ranges as control values. The objective of this study was to evaluate the factors that can affect nail element concentrations for further sample analyses of a group of individuals by applying neutron activation analysis (NAA). Fingernails and toenails collected from adult individuals of both genders, aged 18 to 71 years, living in the Sao Paulo Metropolitan Region were cut in small fragments, cleaned and dried for analyses. Samples and element standards were irradiated for 16 h under a thermal neutron flux of about 4.5 x 10{sup 12} n cm{sup -2} s{sup -1} at the IEA-R1 nuclear research reactor followed by gamma ray spectrometry. Element concentrations for As, Br, Ca, Co, Cr, Cs, Fe, K, La, Na, Rb, Sb, Sc, Se and Zn were determined. For quality control of the analytical results, certified reference materials were analysed and the results showed good accuracy and precision with relative errors and relative standard deviations lower than 5.1 % and 11.6 %, respectively. Preliminary assays indicated that the contribution due to impurities from plastic involucres used in the irradiation as well as those from nail polishes is very low and could be considered negligible. Results from the nail sample cleaning process using distinct procedures indicated that HNO{sub 3} solution may cause sample dissolution. Sample homogeneity was verified by analysis of a sample in

  18. Determination of trace elements in Mesozoic dykes of the Serra do Mar by neutron activation; Determinacao de elementos tracos em diques mesozoicos da Serra do Mar por meio de ativacao com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Vicentini, Caio M.; Marques, Leila S., E-mail: caio.vicentini@usp.br, E-mail: leila@iag.usp.br [Universidade de Sao Paulo (IAG/USP), Sao Paulo, SP (Brazil). Instituto de Astronomia, Geofisica e Ciencias Atmosfericas; Figueiredo, Ana Maria G., E-mail: anamaria@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    The analysis of trace elements such as rare earths, Th, U, Ta, Hf, Ba, Rb and Ba, is a very important tool for petrogenetic studies. In order to study these processes in dykes of Enxame Serra do Mar (Coast of Sao Paulo and Rio de Janeiro), belonging to the Parana Magmatic Province (PMP), one of the most significant provinces of continental basalts in the world, were perform analyzes by neutron activation in these dikes. The technique, employed in Centro de Reator de Pesquisa of the Instituto de Pesquisas Energeticas e Nucleares, provided concentrations of trace elements with accuracy levels of 10% and 9%, which are suitable for petrogenetic studies. Due to the low concentrations of the elements analyzed, the experimental routine sample preparation processes covered very careful to avoid contamination. The samples investigated can be divided into four groups: basic rocks (SiO{sub 2} <55%) with Ti / Y> 500; basic rocks with Ti / Y <500; intermediate rocks (55% 63%). Dikes of intermediate and acid composition only occur at the Sao Sebastiao Island and adjacent coastal region. The concentrations of major and minor elements, as well as the abundance patterns of rare earths and other incompatible elements of these more differentiated rocks, show significant similarities with the type of the volcanic Chapeco, suggesting similar genesis, in other worlds, including also processes of crustal contamination.

  19. Reshaping of computational system for dosimetry in neutron and photons radiotherapy based in stochastic methods - SISCODES; Remodelagem do sistema computacional para dosimetria em radioterapia por neutrons e fotons baseado em metodos estocasticos - SISCODES

    Energy Technology Data Exchange (ETDEWEB)

    Trindade, Bruno Machado

    2011-02-15

    This work shows the remodeling of the Computer System for Dosimetry of Neutrons and Photons in Radiotherapy Based on Stochastic Methods . SISCODES. The initial description and status, the alterations and expansions (proposed and concluded), and the latest system development status are shown. The SISCODES is a system that allows the execution of a 3D computational planning in radiation therapy, based on MCNP5 nuclear particle transport code. The SISCODES provides tools to build a patient's voxels model, to define a treatment planning, to simulate this planning, and to view the results of the simulation. The SISCODES implements a database of tissues, sources and nuclear data and an interface to access then. The graphical SISCODES modules were rewritten or were implemented using C++ language and GTKmm library. Studies about dose deviations were performed simulating a homogeneous water phantom as analogue of the human body in radiotherapy planning and a heterogeneous voxel phantom, pointing out possible dose miscalculations. The Soft-RT and PROPLAN computer codes that do interface with SISCODES are described. A set of voxels models created on the SISCODES are presented with its respective sizes and resolutions. To demonstrate the use of SISCODES, examples of radiation therapy and dosimetry simulations for prostate and heart are shown. Three protocols were simulated on the heart voxel model: Sm-153 filled balloon and P-32 stent, to prevent angioplasty restenosis; and Tl-201 myocardial perfusion, to imaging. Teletherapy with 6MV and 15MV beams were simulated to the prostate, and brachytherapy with I-125 seeds. The results of these simulations are shown on isodose curves and on dose-volume histograms. The SISCODES shows to be a useful tool for research of new radiation therapy treatments and, in future, can also be useful in medical practice. At the end, future improvements are proposed. I hope this work can contribute to develop more effective radiation therapy

  20. Determination of the cell parameters of {beta}-quartz at 1003 K by neutron multiple diffraction; Parametros de rede do quartzo-{beta} a 1003 K determinados por difracao multipla de neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Campos, Luiz Carlos de

    2002-07-01

    In this work, neutron multiple diffraction (NMD) data was employed for the determination of the parameters a and c of the {beta}-quartz hexagonal cell at 1003 K. An experimental 00.1 {beta}-quartz NMD 'Umweg' pattern has been used for the determinations. During the indexing of the {beta}-quartz pattern it was verified that most of the peaks could be classified as either 'good for the determination of the parameter a' or 'good for the determination of the parameter c'. With such a classification, it became possible to employ an iterative process for the determination of both parameters. To attain this purpose, two methods were developed. The first one, named 'absolute method', used angular azimuthal positions of the peaks, related to the origin of the experimental diagram. The second method, named 'relative method', used azimuthal angular differences between two selected peaks. The values obtained for both parameters, in the two methods employed, were found by applying the angular azimuthal positions, for the first method, and the azimuthal angular differences, for the second method, upon appropriate theoretical indexing diagrams. An iterative process was applied in order to obtain the values of the parameters. In this process, the value obtained for one of the parameters was used in the determination of the other parameter. The process continues until both parameters converge. The iterative process was used in both methods. The relative method proved to be better than the absolute method. The best values of the parameters obtained by the relative method were: a 4.99638 {+-} 0.00057 angstrom and c = 5.46119 {+-} 0.00044 angstrom. (author)

  1. Neutron activation analysis applied to the determination of trace elements in human nails; Aplicacao do metodo de analise por ativacao com neutrons a determinacao de elementos traco em unhas humanas

    Energy Technology Data Exchange (ETDEWEB)

    Aguiar, Amilton Reinaldo

    2001-07-01

    There is a considerable interest in the determination of trace elements in human nails in order to use this tissue as a monitor of nutritional and healthy status of individuals, of occupational exposure diseases and of the environmental contamination. In this work, instrumental neutron activation analysis was applied to determine trace elements in finger nail clippings to make comparisons between the elemental concentrations obtained in nails from healthy individuals of a control group and those from cystic fibrosis (CF) patients. Firstly, a protocol for sample collection and preparation for analysis was established. Finger and toe nail samples from CF patients were collected at the Instituto da Crianca of Medicine School, University of Sao Paulo, SP. The nail samples from control group were collected from healthy adults and from children living in Sao Paulo city, SP. These samples were cleaned by stirring them witha a diluted Triton X100 solution and then by washing with distilled water and acetone. The analytical procedure consisted of irradiation nail samples and elemental standards in the IEA-R1m nuclear reactor under thermal neutro flux of about 10{sup 12} n cm{sup -2} s{sup -1}, for short and long period irradiations. The activities of the radionuclides were measured using a gamma-ray spectrometer comprising an hyperpure Ge detector and associated electronic system. The biological reference materials Bovine Liver 1577b and Oyster Tissue 1566a, both from National Institute of Standards and Technology, USA were analysed in order to evaluate the accuracy and precision of the results. The analysis of variance (ANOVA) and F-test at the significance level of 5% were used to make a comparison between the sets of results obtained in this work. In the comparison of the results obtained for finger and toe nails from CF patients, the Br concentrations were higher in finger nails that those obtained for toe nails. For the control group of children, the finger nails

  2. Polarized neutrons

    International Nuclear Information System (INIS)

    Williams, W.G.

    1988-01-01

    The book on 'polarized neutrons' is intended to inform researchers in condensed matter physics and chemistry of the diversity of scientific problems that can be investigated using polarized neutron beams. The contents include chapters on:- neutron polarizers and instrumentation, polarized neutron scattering, neutron polarization analysis experiments and precessing neutron polarization. (U.K.)

  3. Neutron--neutron logging

    International Nuclear Information System (INIS)

    Allen, L.S.

    1977-01-01

    A borehole logging tool includes a steady-state source of fast neutrons, two epithermal neutron detectors, and two thermal neutron detectors. A count rate meter is connected to each neutron detector. A first ratio detector provides an indication of the porosity of the formation surrounding the borehole by determining the ratio of the outputs of the two count rate meters connected to the two epithermal neutron detectors. A second ratio detector provides an indication of both porosity and macroscopic absorption cross section of the formation surrounding the borehole by determining the ratio of the outputs of the two count rate meters connected to the two thermal neutron detectors. By comparing the signals of the two ratio detectors, oil bearing zones and salt water bearing zones within the formation being logged can be distinguished and the amount of oil saturation can be determined. 6 claims, 2 figures

  4. Ultracold neutrons

    International Nuclear Information System (INIS)

    Steenstrup, S.

    Briefly surveys recent developments in research work with ultracold neutrons (neutrons of very low velocity, up to 10 m/s at up to 10 -7 eV and 10 -3 K). Slow neutrons can be detected in an ionisation chamber filled with B 10 F 3 . Very slow neutrons can be used for investigations into the dipole moment of neutrons. Neutrons of large wave length have properties similar to those of light. The limit angle for total reflection is governed by the wave length and by the material. Total reflection can be used to filter ultracold neutrons out of the moderator material of a reactor. Total reflection can also be used to store ultracold neutrons but certain problems with storage have not yet been clarified. Slow neutrons can be made to lose speed in a neutron turbine, and come out as ultracold neutrons. A beam of ultracold neutrons could be used in a neutron microscope. (J.S.)

  5. Evaluation of essential trace elements in preterm and full term milk and childhood formulas by neutron activation analysis; Avaliacao dos teores de elementos essenciais no leite materno de maes de recem-nascidos prematuros e a termo e em formulas infantis por meio da analise por ativacao com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Paola de Souza

    2009-07-01

    Many studies have emphasized the need of trace elements during infancy and their adequate availability in human milk. Deficiency of minor and trace elements can lead to various disorders in infants. During early childhood trace element requirements, are more critical due to faster growth rates. In this study, Ca, Cl, Fe, K, Mg, Mn, Na, Se and Zn were determined in human colostrum samples from mothers of preterm and full-term newborns. Samples were collected by manual expression from the first to the fifth day after birth. After collection, human colostrum samples were frozen and freeze-dried for analyses. Few of the most commonly commercialized were also analyzed. The essential element concentrations were determined in 30 colostrum samples and 17 milk formula brands by Instrumental Neutron Activation Analysis. Multivariate analyses were applied and the results were separated in two clusters. However the separation was not related to the corresponding gestational age. Results of this study showed that the concentration levels of the essential element Ca, K and Na in the milk formula samples analyzed were in agreement with the printed information on the labels. All concentration levels were also within ANVISA and Codex Allimentarius recommended values and thus adequate for infant nutritional needs. (author)

  6. Neutron activation analysis of ancient silver coins; Analyse d'anciennes pieces d'argent par activation neutronique; Nejtronozyj aktivatsionnyj analiz starinnykh serebryanykh monet; Analisis de antiguas monedas de plata por activacion neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Aitken, Martin J; Emeleus, Vera M; Hall, Edward T [Research Laboratory for Archaeology and the History of Art, University of Oxford (United Kingdom); Kraay, Colin M [Heberden Coin Room, Ashmolean Museum, University of Oxford (United Kingdom)

    1962-01-15

    The amounts of gold and copper present as impurities in 500 Creek silver coins of the fifth century B.C. have been determined with a gamma-ray spectrometer, following neutron activation. The coinage from eight cities and kingdoms was studied; the average gold-content for different groups of coins varies between 0.02% and 0.3%, and the copper content between 0.1% and 10%. Evidence about trading connexions and of deliberate debasements of the coinage has been obtained, and several unsuspected plated coins were detected. The gold content was determined by measuring the intensity of the 0.411 MeV gamma-ray from Au{sup 198} (2.69 d); for the copper content the 0.511 MeV positron annihilation radiation from Cu{sup 64} (12.8 h) was used, and for silver the 0.884 MeV gamma-ray from Ag{sup 110m} (253 d). Decay measurements were used as a check of identity. The technique of using total gamma-activity decay curves by themselves is insufficiently sensitive. For accurate work, the importance of approximate facsimile standards is stressed. (author) [French] Apres activation neutronique, on a pu determiner, a l'aide d'un spectrometre gamma, les quantites d'or et de cuivre contenues comme impuretes dans 500 pieces d'argent grecques du cinquieme siecle avant J.C. On a etudie des pieces frappees par huit cites ou royaumes; la teneur moyenne en or des differentes pieces varie de 0,02 a 0,3%, tandis que la teneur en cuivre se situe entre 0,1 et 10%. Ces pieces ont permis, d'une part, de se rendre compte des relations commerciales existant a l'epoque et, d'autre part, de constater que certaines d'entre elles avaient ete deliberement alterees et que plusieurs autres etaient simplement plaquees. On a determine la teneur en or en mesurant l'intensite des rayons gamma de 0,411 MeV emis par l'or-198 (2,69 jours); pour la teneur en cuivre, on a utilise les rayonnements d'annihilation des positons de 0,511 MeV emis par le cuivre-64 (12,8 heures); pour la teneur en argent, les rayons gamma de

  7. Rapid Estimation of Fast-Neutron Doses following Radiation Exposure in Criticality Accidents: The S{sup 32}(n, p)P{sup 32} Reaction in Body Hair; Prompte Evaluation des Doses de Neutrons Rapides apres une Exposition au Rayonnement a la Suite d'Accidents de Criticite: Reaction {sup 32}S(n, p){sup 32}P dans le Systeme Pileux; 0411 042b 0421 0414 ; Evaluacion Acelerada de Dosis de Neutrones Rapidos Despues de una Irradiacion Consecutiva a un Accidente de Criticidad: La Reaccion {sup 32}S(n, p){sup 32}P en el Pelo

    Energy Technology Data Exchange (ETDEWEB)

    Petersen, D. F. [Los Alamos Scientific Laboratory, University of California, Los Alamos, NM (United States)

    1965-06-15

    la zona de localizacion; arroja valores de 0,048*0,005 g de azufre por gramo de pelo, de modo que en las evaluaciones preliminares de dosis se puede emplear como norma la cifra de 5% para la abundancia de azufre sin necesidad de efectuar analisis individuales. En ausencia de una contaminacion externa, facil de eliminar, el pelo contiene menos del 0, 025% de fosforo; como las secciones eficaces de activacion del fosforo y el azufre son similares, la ausencia virtual de fosforo permite emplear el azufre del pelo como detector biologico de umbral para medir flujos neutronicos de energia superior a 2,5 M e V por la reaccion {sup 32}S(n, p){sup 32}P. Se han perfeccionado tecnicas de separacion rapida de radioquimicamente puro para poder evaluar con fines clinicos la exposicion a los neutrones rapidos de las victimas de accidentes de criticidad. Si la contaminacion por productos de fision no es grave se puede efectuar una evaluacion preliminar en el plazo de dos horas; 'mientras que si es necesario eliminarla, el procedimiento requiere aproximadamente seis horas. Los experimentos efectuados con el espectro de fision bien definido de un conjunto critico sin blindar han dado siempre para la dosis -neutronica valores que diferian en menos de 10 Degree-Sign Inverted-Exclamation-Mark o de los hallados por los metodos dosimetricos de control. Ademas, comparando las actividades especificas de muestras de pelo de diversas zonas del cuerpo, se puede determinar la orientacion y la asimetria de la exposicion. La experiencia adquirida en tres accidentes de criticidad mortales ha demostrado que las exposiciones eran siempre marcadamente asimetricas. Asi, pues, las determinaciones del {sup 32}P presente en el pelo suministran datos complementarios muy valiosos que pueden compararse con las evaluaciones de la exposicion neutronica media del organismo entero por medicion del {sup 24}Na contenido en la sangre. Las evaluaciones de los rendimientos de fision, basadas en las geometrias que se

  8. Metabolism of fission products in man: Marshallese experience; Metabolisme des produits de fission radioactifs chez l'homme: donnees recueillies aux iles Marshall; Metabolizm radioaktivnykh produktov deleniya v organizme cheloveka. (dannye obsledovaniya zhite- lej marshal'skikh ostrovov); Metabolismo de productos de fision radiactivos en el hombre: datos obtenidos en los habitantes de las islas Marshall

    Energy Technology Data Exchange (ETDEWEB)

    Cohn, S. H. [Brookhaven National Laboratory, Upton, Long Island, NY (United States)

    1963-02-15

    , produisaient la majeure partie de la dose de rayonnements internes. Apres une annee, les principaux radioisotopes etaient {sup 90}Sr, {sup 137}Cs y {sup 65}Zn. Par la suite, on a mesure periodiquement ces radionucleides et, plus recemment, {sup 60}Co. Depuis 1958, on a pu obtenir, i l'aide d'un appareil portatif de dosage del'activite du corps humain, les spectres gamma d'un certain nombre d'habitants des iles Marshall. L'auteur etudie les resultats de ces enquetes, obtenus au cours des huit dernieres annees. Il presente egalement les resultats d'une tentative faite au debutpour modifier la vitesse d'elimination des produits de fission mixtes chez les autochtones au moyen d'un sel double de calcium et de sodium de l'EDTA. Il etudie enfin le metabolisme des radionucleides et leurs rapports avec les concentrations presentes dans le milieu ambiant. (author) [Spanish] El estudio clinico de los habitantes de las islas Marshall que en 1954 quedaron expuestos accidentalmente a precipitaciones radiactivas posee gran valor cientifico porque, junto con el caso de los pescadores japoneses, constituye la unica fuente de datos sobre el metabolismo de mezclas de productos de fision en el hombre. Al principio, el diagnostico de la contaminacion radiactiva interna se efectuo por analisis radioquimico de los tejidos de animales expuestos simultaneamente. Se encontro que la mayor parte de la dosis de radiacion interna se debia al {sup 89}Sr, {sup 140}Ba, {sup 131}I y sus descendientes de periodo breve, asi como a algunos de los elementos de las tierras raras. Al cabo de un alio,los principales radioisotopos presentes eran el {sup 90}Sr, {sup 137}Cs y {sup 65}Zn. Despues se siguieron midiendo periodicamente estos radionuclidos y, mas recientemente, el {sup 60}Co. Desde 1958, se han obtenido los espectros y de un cierto numero de pobladores de aquellas islas por recuento del organismo entero con un aparato portatil. El informe discute los datos que durante los ultimos ocho anos se han obtenido

  9. Neutron reflectometry

    International Nuclear Information System (INIS)

    Van Well, A.A.

    1999-01-01

    Neutron research where reflection, refraction, and interference play an essential role is generally referred to as 'neutron optics'. The neutron wavelength, the scattering length density and the magnetic properties of the material determine the critical angle for total reflection. The theoretical background of neutron reflection, experimental methods and the interpretation of reflection data are presented. (K.A.)

  10. Study of the shielding for spontaneous fission sources of Californium-252; Estudio de blindaje para fuentes de fision espontanea de Californio-252

    Energy Technology Data Exchange (ETDEWEB)

    Davila R, I

    1991-06-15

    A shielding study is made to attenuate, until maximum permissible levels, the neutrons radiation and photons emitted by spontaneous fission coming from a source of Californium-252. The compound package by a database (Library DLC-23) and the ANISNW code is used, in it version for personal computer. (Author)

  11. Simulating the spectrum of neutrons produced by a radiation beam of high voltage inside an anthropomorphic phantom; Simulacion de espectro de nuetrones producido por un haz de radioterapia de alto voltaje en el interior de un manique antropomorfico

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez-Soto, X.; Amgarou, K.; Langares, J. I.; Munez, J. L.; Mendez, R.; Exposito, M. R.; Gomez, F.; Domingo, C.; Sanche-Doblado, F.

    2011-07-01

    Our project aims to provide a universal method to estimate the dose deposited by neutrons in patients, using an anthropomorphic phantom. Both the detector response as relative biological effectiveness have a strong dependence on the energy spectrum of those, for this reason, a series of simulations were performed to calculate the spectrum of the neutron fluence in 16 representative points within the anthropomorphic phantom Standard for a full course of radiotherapy.

  12. Neutron radiography with ultracold neutrons

    International Nuclear Information System (INIS)

    Bates, J.C.

    1981-01-01

    The neutron transmission factor of very thin films may be low if the neutron energy is comparable to the pseudo-potential of the film material. Surprisingly, perhaps, it is relatively easy to obtain neutrons with such low energies in sufficient numbers to produce neutron radiographs. (orig.)

  13. Neutron Skins and Neutron Stars

    OpenAIRE

    Piekarewicz, J.

    2013-01-01

    The neutron-skin thickness of heavy nuclei provides a fundamental link to the equation of state of neutron-rich matter, and hence to the properties of neutron stars. The Lead Radius Experiment ("PREX") at Jefferson Laboratory has recently provided the first model-independence evidence on the existence of a neutron-rich skin in 208Pb. In this contribution we examine how the increased accuracy in the determination of neutron skins expected from the commissioning of intense polarized electron be...

  14. Problems to be Expected in Disposing of Fission Products from a Possible Nuclear Power Programme; Problemes Eventuels d'Elimination des Produits de Fission dans les Futures Centrales Nucleaires; 0412 0415 0420 041e 042f 0414 ; Problemas que Puede Plantear la Evacuacion de Productos de Fision Resultantes de la Ejecucion de un Programa de Produccion de Energia de Origen Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Dickson, G. K. [Cenral Technical Services, Engineering and Development Group, United Kingdom Atomic Energy Authority, Risley (United Kingdom)

    1960-07-01

    menos precisos cuando se trata de un futuro mas lejano. Los procesos quimicos que sera necesario emplear para los combustibles irradiados dependeran del tipo de combustible, de su grado de combustion, etc. por lo que se supone que cambiaran durante el periodo en cuestion. Por lo tanto, se estudian las cantidades de productos de fision e isotopos pesados que puedan producirse, las formas en que puedan salir de los diversos procesos de elaboracion, y los metodos de que se dispone para manejarlos con garantias de seguridad, bien almacenandolos o evacuandolos. (author) [Russian] V dokumente rassmatrivaetsja tipichnaja programma po atomnoj jenergetike Velikobritanii na posledujushhie neskol'ko desjatiletij. V nem daetsja dostatochno horoshaja ocenka podlezhashhih stroitel'stvu tipov atomnyh reaktorov i tipov gorjuchego, kotoroe budet pervonachal'no ispol'zovat'sja v nih, hotja jetot vopros i javljaetsja menee opredelennym dlja posledujushhego vremeni. Himicheskaja obrabotka, kotoroj neobhodimo podvergnut' obluchennoe gorjuchee, budet zaviset' ot vida gorjuchego, ego vygoranija i t.d. i podvergnetsja izmeneniju vo vremja rassmatrivaemogo perioda vremeni. Pojetomu v dokumente udeljaetsja vnimanie voprosu o kolichestve deljashhihsja materialov i tjazhelyh izotopov, kotorye mogut byt' proizvedeny, o formah, v kotoryh oni okazyvajutsja posle himicheskoj obrabotki, a takzhe voprosu o dostupnyh metodah bezopasnogo obrashhenija s nimi kak posredstvom hranenija v cisternah, tak i posredstvom udalenija. (author)

  15. Biological Effects of Thermal Neutrons and the B{sup 10}(n, {alpha}) Li{sup 7} reaction; Effets Biologiques des Neutrons Thermiques et la Reaction {sup 10}B(n, {alpha}){sup 7}Li; Biologicheskoe dejstvie teplovykh nejtronov i reaktsiya B{sup 10}(n, {alpha}) Li{sup 7}; Efectos Biologicos de los Neutrones Termicos y la Reaccion {sup 10}B(n, {alpha}){sup 7}Li

    Energy Technology Data Exchange (ETDEWEB)

    Archambeau, J. O.; Alcober, V.; Calvo, W. G.; Brenneis, H. [Medical Research Center, Brookhaven National Laboratory, Upton, NY (United States)

    1964-05-15

    astrocytes et d'une alteration de l ' endothelium des capillaires. Il en resulte une deficience marquee en plaquettes, qui vient aggraver les alterations locales. Les animaux meurent d'une hemorragie et/ou d'une lesion du cerveau entre le cinquieme et le neuvieme jour apres l'expo sition. Ces effets sont attribues aux rayons gamma et aux particules alpha produits lors de la capture des neutrons par le bore {sup 10}B(n, {alpha}){sup 7}Li. L'exposition de la peau d'un porc a un flux de 5 x 10{sup 12} n/cm{sup 2} ne provoque aucune modification histologique. Lorsque la peau est irradiee par ce meme flux apres une injection intraveineuse de 35 mg de {sup 10}B/kg de matiere vivante, on constate une radioepidermite classique, qui guerit dans l'espace de 36 a 40 j. Le fractionnement du flux total en huit expositions reparties sur 12 j ne diminue pas la gravite de la reaction, comme c'est le cas pour une irradiation par les rayons gamma. Cet effet est attribue essentiellement a l'action des particules alpha provenant de la capture des neutrons thermiques par le bore. (author) [Spanish] U irradiacion de animales con neutrones termicos procedentes del reactor de investigacion medica (MRR) produce en los tejidos efectos derivados de las radiaciones gamma y otras particulas liberadas en la captura de los neutrones termicos por los elementos del tejido y los materiales protectores, asi como de las radiaciones gamma y los neutrones rapidos generados en el proceso de fision en el cuerpo del reactor. Los resultados globales de la irradiacion con neutrones termicos son funcion del flujo incidente nvt. Como el flujo de neutrones termicos decrece rapidamente dentro del tejido (capa semirreductorasl Approximately-Equal-To 8 cm), las dosis que inciden sobre la superficie deben ser grandes a fin de que la dosis profunda sea suficiente. Las reacciones consecutivas en el pulmon, el intestino, la medula osea y las mucosas se atribuyen principalmente al efe cto de los rayos gamma originados por la

  16. Neutron Dosimetry

    International Nuclear Information System (INIS)

    Vanhavere, F.

    2001-01-01

    The objective of SCK-CEN's R and D programme on neutron dosimetry is to improve the determination of neutron doses by studying neutron spectra, neutron dosemeters and shielding adaptations. In 2000, R and D focused on the contiued investigation of the bubble detectors type BD-PND and BDT, in particular their sensitivity and temperature dependence; the updating of SCK-CEN's criticality dosemeter, the investigation of the characteristics of new thermoluminescent materials and their use in neutron dosemetry; and the investigation of neutron shielding

  17. Neutron Dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Vanhavere, F

    2001-04-01

    The objective of SCK-CEN's R and D programme on neutron dosimetry is to improve the determination of neutron doses by studying neutron spectra, neutron dosemeters and shielding adaptations. In 2000, R and D focused on the contiued investigation of the bubble detectors type BD-PND and BDT, in particular their sensitivity and temperature dependence; the updating of SCK-CEN's criticality dosemeter, the investigation of the characteristics of new thermoluminescent materials and their use in neutron dosemetry; and the investigation of neutron shielding.

  18. Determination of mercury in urine through Neutron activation analysis in dentists, as a measure of occupational exposure; Determinacion de mercurio en orina mediante analisis por activacion neutronica en odontologos, como una medida de exposicion ocupacional

    Energy Technology Data Exchange (ETDEWEB)

    Padilla M, M.A

    2000-07-01

    The mercury level was studied in urine to a dentists group belonging at the Universidad Autonoma del Estado de Mexico to determine the grade of contamination to the exposure of this element during their occupational activity. It was used the Neutron activation analysis which is an analytical method based in the irradiation with neutrons toward a stable nuclide. This can suffer a nuclear transformation to produce a radioactive nuclide and so it will be able to realize a quantitative analysis of itself. The TRIGA Mark III Reactor at the Nuclear Center in Mexico was used to realize this type of analysis due to the neutron fluxes which can be obtained as well as to the facilities in the irradiation of the sample.The purpose of this work is to determine the concentrations of mercury in the occupational exposed personnel such as dentists and so giving the recommendations of safety required to their production. (Author)

  19. Theory of the Influence of Phonon-Phonon and Electron-Phonon Interactions on the Scattering of Neutrons by Crystals; Theorie de l'influence des interactions phonon-phonon et electron-phonon sur la diffusion des neutrons par des cristaux; Teoriya vliyaniya vzaimodejstvij fonon-fonon iehlvktron-fonon na rasseyanie nejtronov kristalla-; Teoria de la influencia de las interacciones fonon-fonon y electron-fonon en la dispersion de neutrones por cristales

    Energy Technology Data Exchange (ETDEWEB)

    Kokkedee, J J.J. [Institute for Theoretical Physics of the University of Utrecht (Netherlands)

    1963-01-15

    appliquee par l'auteur lui permet d'obtenir des formules fermees pour la fonction de diffusion partielle decrivant les pics, qui peuvent etre calculees avec une approximation aussi pousee qu'on le desire. L'auteur a obtenu notamment une expression qui permet de calculer le dephasage et la largeur des raies en puissances de u/d et en fonction de diagrammes connectes simples (u etant le deplacement atomique ou ionique moyen et d la plus petite distance interatomique ou interionique dans le cristal). Des calculs approches donnent une idee de l'ordre de grandeur des effets etudies. (author) [Spanish] Como permite predecir la teoria armonica, el espectro de neutrones dispersados coherente e inelasticamente por un monocristal no conductor consiste, para un angulo de dispersion determinado, en una serie de picos de function delta supetpuestos a un fondo continuo. Los picos corresponden a procesos en que el neutron absorbe o emite un solo fonon; el fondo se debe a procesos de varios fonones. Cuando intervienen fuerzas anarmonicas (interacciones fonon-fonon), los picos de funcion delta se ensanchan, convirtiendose en picos finitos y sus frecuencias centrales se desplazan respecto de los valores armonicos. En el caso de los metales, ademas de las interacciones fonon-fonon existe interaccion entre los fonones y los electrones de conduccion, lo que tambien contribuye al desplazamiento y ensanchamiento de los picos correspondientes a los procesos de un solo fonon. Prosiguiendo trabajos anteriores de Van Hove (quien investigo el caso relativamente sencillo de un cristal no conductor en el estado fundamental (T = 0{sup o}K) ), el autor ha estudiado el desplazamiento y la amplitud de los picos de dispersion resultantes de las mencionadas interacciones aplicando la teoria de las perturbaciones originadas por partfbulas multiples y utilizando ampliamente tecnicas de diagramas. Un requisito indispensable para dicho estudio es la hipotesis de que, sea cual fuere la intensidad de las

  20. Neutron radiography

    International Nuclear Information System (INIS)

    Hrdlicka, Z.

    1977-01-01

    Neutron radiography is a radiographic method using a neutron beam of a defined geometry. The neutron source usually consists of a research reactor, a specialized neutron radiography reactor or the 252 Cf radioisotope source. There are two types of the neutron radiography display system, viz., a system producing neutron radiography images by a photographic process or a system allowing a visual display, eg., using a television monitor. The method can be used wherever X-ray radiography is used except applications in the radiography of humans. The neutron radiography unit at UJV uses the WWR-S reactor as the neutron source and both types of the above mentioned display system. (J.P.)

  1. The neutron

    International Nuclear Information System (INIS)

    Kredov, B.M.

    1979-01-01

    The history of the neutron is displayed on the basis of contributions by scientists who produced outstanding results in neutron research (part 1), of summarizing discoveries and theories which led to the discovery of the neutron and the resulting development of nuclear physics (part 2), and of fundamental papers written by Rutherford, Chadwick, Iwanenko, and others (appendix). Of interest to physicists, historians, and students

  2. Neutron techniques

    International Nuclear Information System (INIS)

    Charlton, J.S.

    1986-01-01

    The way in which neutrons interact with matter such as slowing-down, diffusion, neutron absorption and moderation are described. The use of neutron techniques in industry, in moisture gages, level and interface measurements, the detection of blockages, boron analysis in ore feedstock and industrial radiography are discussed. (author)

  3. Fission Data and Nuclear Technology; Constantes de Fission et Technologie NucleAire; 0414 0410 041d 041d 042b 0415 . 041e 0414 0415 041b 0415 041d 0418 0418 0418 042f 0414 0415 0420 041d 0410 042f 0422 0415 0425 041d 041e 041b 041e 0413 0418 042f ; Datos Sobre la Fision y Tecnologia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Hanna, G. C. [Chalk River Nuclear Laboratories, Chalk River, ON (Canada)

    1965-07-15

    Accurate nuclear data for fissile nuclei are required not only by reactor designers, but also by reactor physicists for the interpretation of integral experiments, e.g. studies of the change of reactivity with irradiation. Some of the requests that have been made for such fission data, and the reasons behind them, are discussed, along with the progress that has been made towards their fulfilment. An attempt is made to outline those areas where better data are required. (author) [French] On a besoin de valeurs exactes des constantes nucleaires concernant les noyaux fissiles, non seulement pour les etudes de reacteurs, mais egalement pour la physique des reacteurs lorsqu'on veut interpreter les experiences integrales, c'est-a-dire dans les etudes sur les modifications de la reactivite avec l'irradiation. L'auteur discute certaines des demandes de renseignements sur les constantes de fission, les raisons pour lesquelles elles ont ete faites et la mesure dans laquelle elles ont pu etre satisfaites. Il s'efforce egalement de delimiter les domaines dans lesquels on aurait besoin de valeurs plus precises. (author) [Spanish] No solo quienes trabajan.en el proyecto de reactores requieren datos nucleares exactos sobre los nucleos fisionables, sino que tambien los fisicos de reactores los necesitan para interpretar los resultados de experimentos integrales, como por ejemplo, en los estudios sobre la variacion de la reactividad en funcion de la irradiacion. El autor describe algunas de las peticiories de datos de esa clase que se han formulado, asi como los adelantos realizados con objeto de satisfacerlas. Tambien indica, en lineas generales, aiquellas esferas en las que se necesitan datos mas amplios y exactos. (author) [Russian] Tochnye jadernye dannye o rasshhepljajushhihsja jadrah neobhodimy ne tol'ko konstruktoram reaktorov, no takzhe i fizikam-reak- torshhikam dlja interpretacii integral'nyh jeksperimentov, to est' dlja izuchenija izmenenija reaktivnosti po mere

  4. Small-Angle Scattering of Neutrons by Iron and Nickel Close to the Curie Point; Diffusion aux petits angles des neutrons par le fer et le nickel au voisinage du point de curie; Rasseyanie nejtronov pod malymi uglami zhelezom i nikelem, blizkikh k tochke kyuri; Dispersion de neutrones en angulos pequenos por el hierro y el niquel cerca del punto de curie

    Energy Technology Data Exchange (ETDEWEB)

    Jacrot, B.; Konstantinovic, J.; Parette, G.; Cribier, D. [Centre d' etudes Nucleaires de Saclay (France)

    1963-01-15

    Recent studies on critical scattering by iron have thrown fresh light on the results obtained previously and shown that: (1) At the Curie point, scattering is inelastic. The Lorentzian form of the lines and their angular dependence establish the existence of a scattering process having the diffusion coefficient 2m {Omega}/n = 7. (2) At the Curie point, the coefficient K{sub 1}{sup 2} is less than 5 x 10{sup -5} A{sup -2}. Iron and nickel have very different angular distribution. Small-angle scattering below T{sub c} has also been studied. (author) [French] De nouveaux travaux sur la diffusion critique par le fer ont permis de completer les resultats obtenus anterieurement. Ils etablissent les faits suivants: 1. Au point de Curie la diffusion est inelastique. La forme lorentzienne des raies et leur dependance angulaire etablissent l'existence d*un processus de diffusion avec un coefficient de diffusion 2m{Omega}/n = 7. 2. Au point de Curie le coefficient K{sub 1}{sup 2} est inferieur a 5 x 10{sup -5} A{sup -2}. La distribution angulaire est tres differente dans le cas du fer et du nickel. On a egalement etudie la diffusion aux petits angles en dessous de T{sub c}. (author) [Spanish] Nuevos trabajos sobre la dispersion critica por el hierro han permitido completar los resultados obtenidos anteriormente. Dichos trabajos prueban los hechos siguientes: 1) La dispersion es inelastica en el punto de Curie. La forma lorentziana de las rayas y su dependencia angular demuestran la existencia de un proceso de dispersion con un coeficiente de dispersion igual a 2m {Omega}/n = 7. 2) En el punto de Curie, el coeficiente K{sub 1}{sup 2} es inferior a 5 x 10{sup -5} A{sup -2}. La distribucion angular es muy diferente en el caso del hierro y del ni quel. Se ha estudiado tambien la dispersion en pequenos angulos por debajo de T{sub c}. (author)

  5. Use of Germanium as comparator and integral monitor of neutron flux in activation analysis; Utilizacion del germanio como comparador y monitor integral de flujo neutronico en analisis por activacion

    Energy Technology Data Exchange (ETDEWEB)

    Furnari, Juan C.; Cohen, Isaac M. [Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Centro Atomico Ezeiza; Arribere, Maria A.; Kestelman, Abraham J. [Comision Nacional de Energia Atomica, San Carlos de Bariloche (Argentina). Centro Atomico Bariloche

    1997-10-01

    The possibility of using germanium as monitor of the thermal and epithermal components of the neutron flux, and comparator in parametric activation analysis, is discussed. The advantages and drawbacks associated to the use of this element are commented on, and the comparison with zirconium, in terms of the determination relative error, is performed. The utilisation of germanium as integral flux monitor, including the fast component of the neutron spectrum, is also discussed. Data corresponding to measurements of k{sub 0} factor for the most relevant gamma transitions from Ge-75 and Be-77 are presented, as well as the results of the reference material analysis, employing germanium as flux monitor and comparator in a simultaneous way. (author). 8 refs., 3 figs., 2 tabs.

  6. Fission-Product Separation as a Final Solution to the Problem of Storing Highly Radioactive Waste; La Separation des Produits de Fission Comme Solution Definitive du Stockage des Dechets Fortement Radioactifs; 0412 042b 0414 ; La Separacion de los Productos de Fision Como Solucion Definitiva del Problema del Almacenamiento de los Desechos de Elevada Radiactividad

    Energy Technology Data Exchange (ETDEWEB)

    Raggenbass, A.; Lefevre, J. [Centre d' Etudes Nucleaires, Saclay (France)

    1963-02-15

    productos de fision concentrados podrian resolverse aislando el cesio-137 y el estroncio-90 con un factor de descontaminacion minimo de 10{sup 4}, lo que, despues de un tratamiento de efluentes ordinario permitiria proceder a la evacuacion al cabo de un periodo de 10 a 20 anos. La finalidad de esta memoria es exponer el estado de la cuestion en 1962. Los progresos realizados en los metodos de separacion del cesio y del estroncio permiten esperar la obtencion del mencionado factor 10{sup 4} en condiciones industrialmente explotables. He aqui los metodos que ofrecen mejores perspectivas: a) Para el cesio-137: la precipitacion mediante el acido fosfowolfrimico, el intercambio a base de una sal de amonio de un heteropoliacido, la fijacion mediante un fosfate de circonio, b) Para el estroncio-90: la precipitacion del oxalato, la extraccion mediante el acido di-2-etilhexil- fosforico, el intercambio a base de sales diversas, sulfato de estroncio, etc. Estos progresos en el terrenorde la quimica, a los que se suman los progresos realizados en el tratamiento industrial de los efluentes, permiten considerar tecnicamente posible la solucion propuesta por Glueckauf. Al mismo tiempo, el desarrollo de la utilizacion de grandes cantidades de productos de fision, particularmente dentro del marco de los programas SNAP, justifica la inversion de capitales que seran recuperados, poit lo menos parcialmente, mediante la venta de los productos fabricados. Es evidente que las fuentes refractarias, de muy alta resistencia frente a todos los agentes exteriores de ataque, constituyen la forma de almacenamiento mas satisfactoria para productos tan peligrosos y de periodo tan prolongado. Los autores consideran, pues, que desde el punto de vista tecnico y psicologico el empleo de fuentes concentradas con abundante revestimiento es el medio de almacenamiento que ofrece mayores garantias. Valdria la pena efectuar un estudio completo y detallado del metodo descrito comparandolo con el metodo de

  7. 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

    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

  8. Characterization of obsidian devices come from San Miguel Ixtapan, Estado de Mexico by Neutron Activation Analysis; Caracterizacion de artefactos de obsidiana provenientes de San Miguel Ixtapan, Estado de Mexico con Analisis por Activacion Neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Almazan T, M.G.; Jimenez R, M.; Monroy G, F.; Tenorio C, D. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2002-07-01

    The Neutron Activation Analysis (NAA) is an efficient multielemental technique for determination of elements in low concentration (ppm), what has been result useful in the study of origin of archaeological material. In this work that technique was used for characterizing obsidian devices coming from the San Miguel Ixtapan site, Estado de Mexico and it was found that these come from three important beds which are: Sierra de Pachuca, Hidalgo, Zinapecuaro and Zinaparo-Varal in the Michoacan state. (Author)

  9. Neutron radiography

    International Nuclear Information System (INIS)

    Hiraoka, Eiichi

    1988-01-01

    The thermal neutron absorption coefficient is essentially different from the X-ray absorption coefficient. Each substance has a characteristic absorption coefficient regardless of its density. Neutron deams have the following features: (1) neutrons are not transmitted efficiently by low molecular weight substances, (2) they are transmitted efficiently by heavy metals, and (3) the transmittance differs among isotopes. Thus, neutron beams are suitable for cheking for foreign matters in heavy metals and testing of composites consisting of both heavy and light materials. A neutron source generates fast neutrons, which should be converted into thermal neutrons by reducing their energy. Major neutron souces include nuclear reactors, radioisotopes and particle accelerators. Photographic films and television systems are mainly used to observe neutron transmission images. Computers are employed for image processing, computerized tomography and three-dimensional analysis. The major applications of neutron radiography include inspection of neclear fuel; evaluation of material for airplane; observation of fuel in the engine and oil in the hydraulic systems in airplanes; testing of composite materials; etc. (Nogami, K.)

  10. Neutron detector

    Science.gov (United States)

    Stephan, Andrew C [Knoxville, TN; Jardret,; Vincent, D [Powell, TN

    2011-04-05

    A neutron detector has a volume of neutron moderating material and a plurality of individual neutron sensing elements dispersed at selected locations throughout the moderator, and particularly arranged so that some of the detecting elements are closer to the surface of the moderator assembly and others are more deeply embedded. The arrangement captures some thermalized neutrons that might otherwise be scattered away from a single, centrally located detector element. Different geometrical arrangements may be used while preserving its fundamental characteristics. Different types of neutron sensing elements may be used, which may operate on any of a number of physical principles to perform the function of sensing a neutron, either by a capture or a scattering reaction, and converting that reaction to a detectable signal. High detection efficiency, an ability to acquire spectral information, and directional sensitivity may be obtained.

  11. Fusion neutronics

    CERN Document Server

    Wu, Yican

    2017-01-01

    This book provides a systematic and comprehensive introduction to fusion neutronics, covering all key topics from the fundamental theories and methodologies, as well as a wide range of fusion system designs and experiments. It is the first-ever book focusing on the subject of fusion neutronics research. Compared with other nuclear devices such as fission reactors and accelerators, fusion systems are normally characterized by their complex geometry and nuclear physics, which entail new challenges for neutronics such as complicated modeling, deep penetration, low simulation efficiency, multi-physics coupling, etc. The book focuses on the neutronics characteristics of fusion systems and introduces a series of theories and methodologies that were developed to address the challenges of fusion neutronics, and which have since been widely applied all over the world. Further, it introduces readers to neutronics design’s unique principles and procedures, experimental methodologies and technologies for fusion systems...

  12. Neutron spectometers

    International Nuclear Information System (INIS)

    Poortmans, F.

    1977-01-01

    Experimental work in the field of low-energy neutron physics can be subdivided into two classes: 1)Study of the decay process of the compound-nucleus state as for example the study of the capture gamma rays and of the neutron induced fission process; 2)Study of the reaction mechanism, mainly by measuring the reaction cross-sections and resonance parameters. These neutron cross-sections and resonance parameters are also important data required for many technological applications especially for reactor development programmes. In general, the second class of experiments impose other requirements on the neutron spectrometer than the first class. In most cases, a better neutron energy resolution and a broader neutron energy range are required for the study of the reaction mechanism than for the study of various aspects of the decay process. (author)

  13. Analysis of relation between the mutation frequencies and somatic recombination induced by neutrons and the age of D. Melanogaster larvae; Analisis de la relacion entre las frecuencias de mutacion y recombinacion somaticas inducidas por neutrones y la edad de las larvas en D. Melanogaster

    Energy Technology Data Exchange (ETDEWEB)

    Guzman R, J; Zambrano A, F; Paredes G, L; Delfin L, A; Quiroz R, C [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1998-07-01

    Neutrons are subatomic particles with neutral electric charge, equal zero, which are emitted during the fissile material fission in nuclear reactors. It is known a little about biological effects induced by neutrons. There is a world interest in the use of reactors and accelerators for patients radiotherapy using neutrons with the purpose to destroy malignant cells of deep tumours where traditional methods have not given satisfactory results. There for it is required to do wide studies of biological effects of neutrons as well as their dosimetry. It was used the Smart test (Somatic Mutation and Recombination Test) of D. Melanogaster for quantifying the mutation induction and somatic recombination induced by neutrons of the National Institute of Nuclear Research reactor, at power of 300 and 1000 k W, with equivalent doses calculated 95.14 and 190.2 Sv for 300 k W and of 25.64 and 51.29 Sv for 1000 k W, using larvae with 72 or 96 hours aged. It was observed a linear relation between equivalent dose and genetic effects frequency, these last were greater when the reactor power was 1000 k W than those 300 k W. It was observed too that the damage was greater in 96 hours larvae than those 72 hours. The stain size presented an inverse relation with respect to larvae age. It is concluded that the Smart system is sensitive to neutrons effect and it responds of a directly proportional form to radiation dose, as well as to dose rate. It is noted more the effect when are used larvas in pre pupa stage where the irradiation target (imagal cells) is greater. The Smart is sensitive to damage induced by neutrons , thus can be used to studying its direct biological effects or by the use of chemical modulators. (Author)

  14. Neutron exposure

    International Nuclear Information System (INIS)

    Prillinger, G.; Konynenburg, R.A. van

    1998-01-01

    As a result of the popularity of the Agencies report 'Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels' of 1975, it was decided that another report on this broad subject would be of use. In this report, background and contemporary views on specially identified areas of the subject are considered as self-contained chapters, written by experts. In chapter 6, LWR-PV neutron transport calculations and dosimetry methods and how they are combined to evaluate the neutron exposure of the steel of pressure vessels are discussed. An effort to correlate neutron exposure parameters with damage is made

  15. Atmospheric neutrons

    International Nuclear Information System (INIS)

    Preszler, A.M.; Moon, S.; White, R.S.

    1976-01-01

    Additional calibrations of the University of California double-scatter neutron and additional analysis corrections lead to the slightly changed neutron fluxes reported here. The theoretical angular distributions of Merker (1975) are in general agreement with our experimental fluxes but do not give the peaks for vertical upward and downward moving neutrons. The theoretical neutron escape current J 2 /sub pi/ (Merker, 1972; Armstrong et al., 1973) is in agreement with the experimental values from 10 to 100 MeV. Our experimental fluxes agree with those of the Kanbach et al. (1974) in the overlap region from 70 to 100 MeV

  16. Neutron Albedo

    CERN Document Server

    Ignatovich, V K

    2005-01-01

    A new, algebraic, method is applied to calculation of neutron albedo from substance to check the claim that use of ultradispersive fuel and moderator of an active core can help to gain in size and mass of the reactor. In a model of isotropic distribution of incident and reflected neutrons it is shown that coherent scattering on separate grains in the case of thermal neutrons increases transport cross section negligibly, however it decreases albedo from a wall of finite thickness because of decrease of substance density. A visible increase of albedo takes place only for neutrons with wave length of the order of the size of a single grain.

  17. Utilization of shear stress for determination of activation energy of the defects created by neutron irradiation; Utilizacion de la tension de fluencia en la determinacion de la energia de activacion de defectos producidos por irradiacion neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, Hector C.; Miralles, Monica [Comision Nacional de Energia Atomica, Buenos Aires (Argentina)

    1996-07-01

    This paper describes an experimental technique used for the determination thermodynamical parameters such as activation energy using the thermal annealing of increments of Critical resolved Shear Stress of the defects created by neutron irradiation at 77 K. The doses chosen for this work was 3.1 x 10 {sup 16} n/cm{sup 2} since the defects are stable to plastic deformation and the cascades of atomic displacements do not overlap. Specimens without any prior deformation were used allowing then the single addition of the initial stress to that due to the created defects. (author)

  18. Spectra and absorbed dose by photo-neutrons in a solid water mannequin exposed to a Linac of 15 MV; Espectros y dosis absorbida por fotoneutrones en un maniqui de agua solida expuesta a una Linac de 15 MV

    Energy Technology Data Exchange (ETDEWEB)

    Benites R, J. [Centro Estatal de Cancerologia de Nayarit, Servicio de Seguridad Radiologica, Calz. de la Cruz 118 Sur, 63000 Tepic, Nayarit (Mexico); Vega C, H. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Apdo. Postal 336, 98000 Zacatecas (Mexico); Velazquez F, J., E-mail: jlbenitesr@prodigy.net.mx [Universidad Autonoma de Nayarit, Posgrado en Ciencias Biologico Agropecuarias, Carretera Tepic-Compostela Km 9, 63780 Jalisco-Nayarit (Mexico)

    2012-10-15

    Using Monte Carlo methods was modeled a solid water mannequin; according to the ICRU 44 (1989), Tissue substitutes in radiation dosimetry and measurements, of the International Commission on Radiation Units and Measurements; Report 44. This material Wt 1 is made of H (8.1%), C (67.2%), N (2.4%), O (19.9%), Cl (0.1%), Ca (2.3%) and its density is of 1.02 gr/cm{sup 3}. The mannequin was put instead of the patient, inside the treatment room and the spectra and absorbed dose were determined by photo-neutrons exposed to a Linac of 15 MV. (Author)

  19. Analysis by neutron activation in moss samples for the determination of Cr, Se, As and Hg; Analisis por activacion neutronica en muestras de musgos para la determinacion de Cr, Se, As y Hg

    Energy Technology Data Exchange (ETDEWEB)

    Mejia C, R.; Garcia R, G. [Instituto Tecnologico de Toluca, Departamento de Posgrado, Av. Tecnologico s/n, Fraccionamiento La Virgen, 52149 Metepec, Estado de Mexico (Mexico); Lopez R, C.; Avila P, P.; Longoria G, L. C., E-mail: rosario.mejia@inin.gob.mx [ININ, Departamento del Reactor, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2012-10-15

    This research work, presents a study of environmental monitoring in the Metropolitan Area of Toluca Valley using as bio-monitors to the mosses (bryophytes) native of different sites, analyzing the concentrations of As, Cr, Hg and Se, present in its structure. The analysis technique used to identify and to quantify to these elements was the Analysis by Neutron Activation, a nuclear analytic technique that allowed determining the concentrations at track level for its great versatility. Likewise the morphological study of the bryophyte Leskea angustata is presented by scanning electron microscopy. (Author)

  20. The use of neutron diffraction for the determination of the in-depth residual stresses profile in weld coatings; A utilizacao da difracao de neutroes na determinacao do perfil de tensoes residuais em revestimentos por soldadura

    Energy Technology Data Exchange (ETDEWEB)

    Marques, Maria Jose; Batista, A.C.; Nobre, J.P. [Universidade de Coimbra (Portugal). Dept. de Fisica. Centro de Estudos de Materiais por Difraccao de Raios X (CEMDRX); Loureiro, Altino [Universidade de Coimbra (Portugal). Dept. de Engenharia Mecanica. Centro de Engenharia Mecanica (CEMUC); Kornmeier, Joana R., E-mail: mjvaz@fe.up.pt [Technische Universitaet Muenchen, Garching (Germany). FRM II

    2013-04-15

    The neutron diffraction is a non-destructive technique, particularly suitable for the analysis of residual stress fields in welds. The technique is used in this article to study ferritic samples, coated by submerged arc welding using stainless steel filler metals. This procedure is often used for manufacturing process equipment for chemical and nuclear industries, for ease of implementation and economic reasons. The main disadvantage of that processes is the cracking phenomenon that often occurs at the interface between the base material and coatings, which can be minimized by performing post-weld stress relief heat treatments. The samples analyzed in this study were made of carbon steel plates, coated by submerged arc welding two types of stainless steel filler metals. For the first layer was used one EN 12 072 - S 2 U 23 12 electrode, while for the second and third layers were used an EN 12 072 - 19 12 3 S L electrode. After cladding, the samples were submitted to a post-weld heat treatment for 1 hour at 620 deg C. The residual stress profiles obtained by neutron diffraction evidence the relaxation of residual stress given by the heat treatment. (author)

  1. Neutron stimulated emission computed tomography applied to the assessment of calcium deposition due to the presence of microcalcifications associated with breast cancer; Tomografia computadorizada de emissao estimulada por neutrons aplicada para avaliar a deposicao de calcio devido a presenca de microcalcificacoes associadas ao cancer de mama

    Energy Technology Data Exchange (ETDEWEB)

    Viana, Rodrigo S.S.; Yoriyaz, Helio [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, (SP) (Brazil)

    2011-07-01

    In this paper we presented an application of the Neutron Stimulated Emission Computed Tomography (NSECT), which uses a thin beam of fast neutrons to stimulate stable nuclei in a sample, emitting characteristic gamma radiation. The photon energy is unique and it is used to identify the emitting nuclei. This technique was applied for evaluating the calcium isotopic composition changing due to the development of breast microcalcifications. A particular situation was simulated in which clustered microcalcifications were modeled with diameters less than 1.40 mm. In this case, neutron beam breast spectroscopy was successful in detecting the counting changes in the photon emission spectra for energies, which are characteristics of 4{sup 0C}a isotope in a low deposited dose rate. (author)

  2. Neutron dosimetry; Dosimetria de neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Fratin, Luciano

    1993-12-31

    A neutron irradiation facility was designed and built in order to establish a procedure for calibrating neutron monitors and dosemeters. A 185 GBq {sup 241} Am Be source of known is used as a reference source. The irradiation facility using this source in the air provides neutron dose rates between 9 nSv s{sup -1} and 0,5 {sup {mu}}Sv s{sup -1}. A calibrated 50 nSv s{sup -1} thermal neutron field is obtained by using a specially designed paraffin block in conjunction with the {sup 241} Am Be source. A Bonner multisphere spectrometer was calibrated, using a procedure based on three methods proposed by international standards. The unfold {sup 241} Am Be neutron spectrum was determined from the Bonner spheres data and resulted in a good agreement with expected values for fluence rate, dose rate and mean energy. A dosimetric system based on the electrochemical etching of CR-39 was developed for personal dosimetry. The dosemeter badge using a (n,{alpha}) converter, the etching chamber and high frequency power supply were designed and built specially for this project. The electrochemical etching (ECE) parameters used were: a 6N KOH solution, 59 deg C, 20 kV{sub pp} cm{sup -1}, 2,0 kHz, 3 hours of ECE for thermal and intermediate neutrons and 6 hours for fast neutrons. The calibration factors for thermal, intermediate and fast neutrons were determined for this personal dosemeter. The sensitivities determined for the developed dosimetric system were (1,46{+-} 0,09) 10{sup 4} tracks cm{sup -2} mSv{sup -1} for thermal neutrons, (9{+-}3) 10{sup 2} tracks cm{sup -2} mSV{sup -1} for intermediate neutrons and (26{+-}4) tracks cm{sup -2} mSv{sup -1} for fast neutrons. The lower and upper limits of detection were respectively 0,002 mSv and 0,6 mSv for thermal neutrons, 0,04 mSv and 8 mSv for intermediate neutrons and 1 mSv and 12 mSv for fast neutrons. In view of the 1990`s ICRP recommendations, it is possible to conclude that the personal dosemeter described in this work is

  3. Neutron dosimetry; Dosimetria de neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Fratin, Luciano

    1994-12-31

    A neutron irradiation facility was designed and built in order to establish a procedure for calibrating neutron monitors and dosemeters. A 185 GBq {sup 241} Am Be source of known is used as a reference source. The irradiation facility using this source in the air provides neutron dose rates between 9 nSv s{sup -1} and 0,5 {sup {mu}}Sv s{sup -1}. A calibrated 50 nSv s{sup -1} thermal neutron field is obtained by using a specially designed paraffin block in conjunction with the {sup 241} Am Be source. A Bonner multisphere spectrometer was calibrated, using a procedure based on three methods proposed by international standards. The unfold {sup 241} Am Be neutron spectrum was determined from the Bonner spheres data and resulted in a good agreement with expected values for fluence rate, dose rate and mean energy. A dosimetric system based on the electrochemical etching of CR-39 was developed for personal dosimetry. The dosemeter badge using a (n,{alpha}) converter, the etching chamber and high frequency power supply were designed and built specially for this project. The electrochemical etching (ECE) parameters used were: a 6N KOH solution, 59 deg C, 20 kV{sub pp} cm{sup -1}, 2,0 kHz, 3 hours of ECE for thermal and intermediate neutrons and 6 hours for fast neutrons. The calibration factors for thermal, intermediate and fast neutrons were determined for this personal dosemeter. The sensitivities determined for the developed dosimetric system were (1,46{+-} 0,09) 10{sup 4} tracks cm{sup -2} mSv{sup -1} for thermal neutrons, (9{+-}3) 10{sup 2} tracks cm{sup -2} mSV{sup -1} for intermediate neutrons and (26{+-}4) tracks cm{sup -2} mSv{sup -1} for fast neutrons. The lower and upper limits of detection were respectively 0,002 mSv and 0,6 mSv for thermal neutrons, 0,04 mSv and 8 mSv for intermediate neutrons and 1 mSv and 12 mSv for fast neutrons. In view of the 1990`s ICRP recommendations, it is possible to conclude that the personal dosemeter described in this work is

  4. Estimation of the contribution by neutrons to the equivalent dose for exposed occupationally personnel and people in medical use facilities: X rays of equal or superior energy to 10 MV; Estimacion de la contribucion por neutrones a la dosis equivalente para personal ocupacionalmente expuesto y publico en instalaciones de uso medico: rayos X de energia igual y/o superior a 10 MV

    Energy Technology Data Exchange (ETDEWEB)

    Ortega J, R.; Reyes S, M. A. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan 779, Col. Narvarte, 03020 Mexico D. F. (Mexico); Moranchel y R, M., E-mail: rojimenez@cnsns.gob.mx [IPN, Escuela Superior de Fisica y Matematicas, Departamento de Ingenieria Nuclear, Av. Instituto Politecnico Nacional s/n, U. P. Adolfo Lopez Mateos, Edif. 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico)

    2013-10-15

    In Mexico the use of electron accelerators for treating cancerous tumors had grown enormously in the last decade. When the treatments are carried out with X-ray beam energy below 10 MV the design of the shielding of the radioactive facility is determined by analyzing the interaction of X-rays, which have a direct impact and dispersion, with materials of the facility. However, when it makes use of X-ray beam energy equal to or greater than 10 MV the neutrons presence is imminent due to their generation by the interaction of the primary beam X-ray with materials head of the accelerator and of the table of treatment, mainly. In these cases, the design and calculation of shielding considers the generation of high-energy neutrons which contribute the equivalent dose that public and occupationally staff exposed (POE) will receive in the areas surrounding the facility radioactive. However, very few measurements have been performed to determine the actual contribution to the neutron dose equivalent received by POE and public during working hours. This paper presents and estimate of the actual contribution of the neutron dose equivalent received by public and POE facilities in various radioactive medical use, considering many factors. To this end, measurements were made of the equivalent dose by using a neutron monitor in areas surrounding different radioactive installations (of Mexico) which used electron accelerators medical use during treatment with X-ray beam energy equal to or greater than 10 MV. The results are presented after a statistical analysis of a wide range of measures in order to estimate more reliability real contribution of the neutron dose equivalent for POE and the public. (author)

  5. Estimation of the contribution of neutrons to the equivalent dose for personnel occupationally exposed and public in medical facilities: X-ray with energy equal or greater than 10MV; Estimacion de la contribucion por neutrones a la dosis equivalente para personal ocupacionalmente expuesto y publico en instalaciones de uso medico: rayos X de energia igual y/o superior a 10MV

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, Alfonso Mayer; Jimenez, Roberto Ortega; Sanchez, Mario A. Reyes, E-mail: amgesfm@hotmail.com, E-mail: rojimenez@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS), Mexico, D.F. (Mexico); Moranchel y Mejia, Mario, E-mail: mmoranchel@ipn.mx [Instituto Politecnico Nacional (ESFM/IPN), Mexico, D.F. (Mexico). Escuela Superior de Fisica y Matematicas. Departamento de lngenieria Nuclear

    2013-07-01

    In Mexico the use of electron accelerators for treating cancerous tumors had grown enormously in the last decade. When the treatments are carried out with X-ray beam energy below 10 MV the design of the shielding of the radioactive facility is determined by analyzing the interaction of X-rays, which have a direct impact and dispersion, with materials of the facility. However, when it makes use of X-ray beam energy equal to or greater than 10 MV the neutrons presence is imminent due to their generation by the interaction of the primary beam X-ray with materials head of the accelerator and of the table of treatment, mainly. In these cases, the design and calculation of shielding considers the generation of high-energy neutrons which contribute the equivalent dose that public and Occupationally Staff Exposed (POE) will receive in the areas surrounding the facility radioactive. However, very few measurements have been performed to determine the actual contribution to the neutron dose equivalent received by POE and public during working hours. This paper presents an estimate of the actual contribution of the neutron dose equivalent received by public and POE facilities in various radioactive medical use, considering many factors. To this end, measurements were made of the equivalent dose by using a neutron monitor in areas surrounding different radioactive installations (of Mexico) which used electron accelerators medical use during treatment with X-ray beam energy equal to or greater than 10 MV. The results are presented after a statistical analysis of a wide range of measures in order to estimate more reliability real contribution of the neutron dose equivalent for POE and the public. (author)

  6. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    A safety rod for a nuclear reactor has an inner end portion having a gamma absorption coefficient and neutron capture cross section approximately equal to those of the adjacent shield, a central portion containing materials of high neutron capture cross section and an outer end portion having a gamma absorption coefficient at least equal to that of the adjacent shield

  7. Neutron polarization

    International Nuclear Information System (INIS)

    Firk, F.W.K.

    1976-01-01

    Some recent experiments involving polarized neutrons are discussed; they demonstrate how polarization studies provide information on fundamental aspects of nuclear structure that cannot be obtained from more traditional neutron studies. Until recently, neutron polarization studies tended to be limited either to very low energies or to restricted regions at higher energies, determined by the kinematics of favorable (p, vector n) and (d, vector n) reactions. With the advent of high intensity pulsed electron and proton accelerators and of beams of vector polarized deuterons, this is no longer the case. One has entered an era in which neutron polarization experiments are now being carried out, in a routine way, throughout the entire range from thermal energies to tens-of-MeV. The significance of neutron polarization studies is illustrated in discussions of a wide variety of experiments that include the measurement of T-invariance in the β-decay of polarized neutrons, a search for the effects of meson exchange currents in the photo-disintegration of the deuteron, the determination of quantum numbers of states in the fission of aligned 235 U and 237 Np induced by polarized neutrons, and the double- and triple-scattering of fast neutrons by light nuclei

  8. Neutron holography

    International Nuclear Information System (INIS)

    Beynon, T.D.

    1986-01-01

    the paper concerns neutron holography, which allows an image to be constructed of the surfaces, as well as the interiors, of objects. The technique of neutron holography and its applications are described. Present and future use of the method is briefly outlined. (U.K.)

  9. Calibration of SPND/Rhodium device for mapping the neutron fluence in the IEA-R1 reactor by means of the activation foil method; Calibracao de um dispositivo de mapeamento de fluxo de neutrons - SNPD/Rodio no reator IEA-R1, por meio do metodo de ativacao de folhas

    Energy Technology Data Exchange (ETDEWEB)

    Ricci Filho, Walter; Dias, Mauro S.; Tondin, Julio B.M.; Koskinas, Marina F. [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

    2002-07-01

    The IEA-R1 reactor has undergone a modernization to increase its operating power to 5 MW, in order to allow a more efficient production of radioisotopes. The objective of this work is to provide the reactor with flux monitoring device using a rhodium Self-Powered Neutron Detector (SPND). The work presents the results obtained with Rhodium-SPND in several irradiation positions inside the reactor core. A calibration procedure has been performed by means of {sup 197} Au activation foils, with and without cadmium cover, in order do measure the thermal and epithermal neutron fluxes. (author)

  10. Neutron source

    International Nuclear Information System (INIS)

    Cason, J.L. Jr.; Shaw, C.B.

    1975-01-01

    A neutron source which is particularly useful for neutron radiography consists of a vessel containing a moderating media of relatively low moderating ratio, a flux trap including a moderating media of relatively high moderating ratio at the center of the vessel, a shell of depleted uranium dioxide surrounding the moderating media of relatively high moderating ratio, a plurality of guide tubes each containing a movable source of neutrons surrounding the flux trap, a neutron shield surrounding one part of each guide tube, and at least one collimator extending from the flux trap to the exterior of the neutron source. The shell of depleted uranium dioxide has a window provided with depleted uranium dioxide shutters for each collimator. Reflectors are provided above and below the flux trap and on the guide tubes away from the flux trap

  11. Neutron transport

    International Nuclear Information System (INIS)

    Berthoud, Georges; Ducros, Gerard; Feron, Damien; Guerin, Yannick; Latge, Christian; Limoge, Yves; Santarini, Gerard; Seiler, Jean-Marie; Vernaz, Etienne; Coste-Delclaux, Mireille; M'Backe Diop, Cheikh; Nicolas, Anne; Andrieux, Catherine; Archier, Pascal; Baudron, Anne-Marie; Bernard, David; Biaise, Patrick; Blanc-Tranchant, Patrick; Bonin, Bernard; Bouland, Olivier; Bourganel, Stephane; Calvin, Christophe; Chiron, Maurice; Damian, Frederic; Dumonteil, Eric; Fausser, Clement; Fougeras, Philippe; Gabriel, Franck; Gagnier, Emmanuel; Gallo, Daniele; Hudelot, Jean-Pascal; Hugot, Francois-Xavier; Dat Huynh, Tan; Jouanne, Cedric; Lautard, Jean-Jacques; Laye, Frederic; Lee, Yi-Kang; Lenain, Richard; Leray, Sylvie; Litaize, Olivier; Magnaud, Christine; Malvagi, Fausto; Mijuin, Dominique; Mounier, Claude; Naury, Sylvie; Nicolas, Anne; Noguere, Gilles; Palau, Jean-Marc; Le Pallec, Jean-Charles; Peneliau, Yannick; Petit, Odile; Poinot-Salanon, Christine; Raepsaet, Xavier; Reuss, Paul; Richebois, Edwige; Roque, Benedicte; Royer, Eric; Saint-Jean, Cyrille de; Santamarina, Alain; Serot, Olivier; Soldevila, Michel; Tommasi, Jean; Trama, Jean-Christophe; Tsilanizara, Aime; Behar, Christophe; Provitina, Olivier; Lecomte, Michael; Forestier, Alain; Bender, Alexandra; Parisot, Jean-Francois; Finot, Pierre

    2013-10-01

    This bibliographical note presents a reference book which addresses the study of neutron transport in matter, the study of conditions for a chain reaction and the study of modifications of matter composition due to nuclear reactions. This book presents the main nuclear data, their measurement, assessment and processing, and the spallation. It proposes an overview of methods applied for the study of neutron transport: basic equations and their derived forms, deterministic methods and Monte Carlo method of resolution of the Boltzmann equation, methods of resolution of generalized Bateman equations, methods of time resolution of space kinetics coupled equations. It presents the main calculation codes, discusses the qualification and experimental aspects, and gives an overview of neutron transport applications: neutron transport calculation of reactors, neutron transport coupled with other disciplines, physics of fuel cycle, criticality

  12. Design and building of a homemade sample changer for automation of the irradiation in neutron activation analysis technique; Diseno y construccion de un prototipo de intercambiador para la automatizacion de la tecnica de analisis por activacion neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Gago, Javier; Hernandez, Yuri; Baltuano, Oscar; Bedregal, Patricia [Direccion de Investigacion y Desarrollo, Instituto Peruano de Energia Nuclear, Lima (Peru); Lopez, Yon [Universidad Nacional de Ingenieria, Lima (Peru); Urquizo, Rafael [Universidad Tecnologica del Peru, Lima (Peru)

    2014-07-01

    Because the RP-10 research reactor operates during weekends, it was necessary to design and build a sample changer for irradiation as part of the automation process of neutron activation analysis technique. The device is formed by an aluminum turntable disk which can accommodate 19 polyethylene capsules, containing samples to be sent using the pneumatic transfer system from the laboratory to the irradiation position. The system is operate by a control switchboard to send and return capsules in a variable preset time and by two different ways, allowing the determination of short, medium and long lived radionuclides. Also another mechanism is designed called 'exchange valve' for changing travel paths (pipelines) allowing the irradiated samples to be stored for a longer time in the reactor hall. The system design has allowed complete automation of this technique, enabling the irradiation of samples without the presence of an analyst. The design, construction and operation of the device is described and presented in this article. (authors).

  13. Determination of Th and U by neutron activation for gamma spectrometry calibration in situ; Determinacion de Th y U por activacion neutronica para calibracion de espectrometria gamma in situ

    Energy Technology Data Exchange (ETDEWEB)

    Nava M, F.; Rios M, C.; Mireles G, F.; Saucedo A, S.; Davila R, I.; Pinedo, J. L. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98060 Zacatecas (Mexico); Landsberger, S., E-mail: iqnava@hotmail.com [University of Texas at Austin, Nuclear Engineering Teaching Laboratory, Pickle Research Campus, R9000 Austin, Texas 78712 (United States)

    2012-10-15

    Using the analysis by neutron activation to determine the profile of the thorium and uranium concentration calibration factors were obtained for their use in the gamma spectrometry in situ. Three sites were selected (San Ramon, Villa de Cos y la Zacatecana) and the analysis by activation was development in the Laboratory of Nuclear Engineering Teaching of the Texas University in Austin with the nuclear reactor Ut-TRIGA. Starting from the gamma spectra in situ, the areas of normalized photo-pick of the radioisotopes were: {sup 208}Tl and {sup 228}Ac for the thorium series and {sup 214}Pb and {sup 214}Bi for the uranium series. The averages of the factors found in units of (cpm/Bq/Kg) are of 105.63{+-}8.32 and 75.87{+-}4.61 for the thorium and uranium, respectively. (Author)

  14. Neutron therapy

    International Nuclear Information System (INIS)

    Riesler, Rudi

    1995-01-01

    Standard radiotherapy uses Xrays or electrons which have low LET (linear energy transfer); in contrast, particles such as neutrons with high LET have different radiobiological responses. In the late 1960s, clinical trials by Mary Catterall at the Hammersmith Hospital in London indicated that fast neutron radiation had clinical advantages for certain malignant tumours. Following these early clinical trials, several cyclotron facilities were built in the 1980s for fast neutron therapy, for example at the University of Washington, Seattle, and at UCLA. Most of these newer machines use extracted cyclotron proton beams in the range 42 to 66 MeV with beam intensities of 15 to 60 microamps. The proton beams are transported to dedicated therapy rooms, where neutrons are produced from beryllium targets. Second-generation clinical trials showed that accurate neutron beam delivery to the tumour site is more critical than for photon therapy. In order to achieve precise beam geometries, the extracted proton beams have to be transported through a gantry which can rotate around the patient and deliver beams from any angle; also the neutron beam outline (''field shape'') must be adjusted to extremely irregular shapes using a flexible collimation system. A therapy procedure has to be appropriately organized, with physicians, radiotherapists, nurses, medical physicists and other staff in attendance; other specialized equipment, such as CT or MRI scanners and radiation simulators must be made available. Neutron therapy is usually performed only in radiation oncology departments of major medical centres

  15. Neutron radiography

    International Nuclear Information System (INIS)

    Alaa eldin, M.T.

    2011-01-01

    The digital processing of the neutron radiography images gives the possibility for data quantification. In this case an exact relation between the measured neutron attenuation and the real macroscopic attenuation coefficient for every point of the sample is required. The assumption that the attenuation of the neutron beam through the sample is exponential is valid only in an ideal case where a monochromatic beam, non scattering sample and non background contribution are assumed. In the real case these conditions are not fulfilled and in dependence on the sample material we have more or less deviation from the exponential attenuation law. Because of the high scattering cross-sections of hydrogen (σs=80.26 barn) for thermal neutrons, the problem with the scattered neutrons at quantitative radiography investigations of hydrogenous materials (as PE, Oil, H 2 O, etc) is not trivial. For these strong scattering materials the neutron beam attenuation is no longer exponential and a dependence of the macroscopic attenuation coefficient on the material thickness and on the distance between the sample and the detector appears. When quantitative radiography (2 D) or tomography investigations (3 D) are performed, some image correction procedures for a description of the scattering effect are required. This thesis presents a method that can be used to enhance the neutron radiography image for objects with high scattering materials like hydrogen, carbon and other light materials. This method uses the Monte Carlo code, MCNP5, to simulate the neutron radiography process and get the flux distribution for each pixel of the image and determine the scattered neutrons distribution that causes the image blur and then subtract it from the initial image to improve its quality.

  16. Neutronics codes

    International Nuclear Information System (INIS)

    Buckel, G.

    1983-01-01

    The objectives are the development, testing and cultivation of reliable, efficient and user-optimized neutron-physical calculation methods and conformity with users' requirements concerning design of power reactors, planning and analysis of experiments necessary for their protection as well as research on physical key problems. A short outline of available computing programmes for the following objectives is given: - Provision of macroscopic group constants, - Calculation of neutron flux distribution in transport theory and diffusion approximation, - Evaluation of neutron flux-distribution, - Execution of disturbance calculations for the determination reactivity coefficients, and - graphical representation of results. (orig./RW) [de

  17. Crystal Dynamics from Neutron Spectrometry; Etude de la dynamique des cristaux par la spectrometrie neutronique; Izuchenie voprosov dinamiki kristallov metodami nejtronnoj spektrometrii; Estudio de la dinamica de redes cristalinas por espectrometria neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Woods, A. D.B. [Atomic Energy of Canada Ltd., Chalk River, ON (Canada)

    1963-01-15

    This paper reviews investigations carried out at Chalk River on the lattice dynamics of various crystals including lead, sodium, alkali halides, semi-conductors, and other more complex compounds. Analysis of the low temperature results (-{approx}100{sup o}K) gives considerable insight into the nature of the interatomic forces. In sodium, a simple metal, the interatomic forces are very nearly derivable from a potential. Lead, a more complicated metal, has extremely long range forces accompanied by strong electronic effects. At higher temperatures anharmonic effects are very pronounced in both metals, especially in lead. The alkali halide results can be interpreted on a ''shell'' model, with polarizable ions. Even at low temperature neutron groups corresponding to the longitudinal optical modes. (author) [French] Dans ce memoire, l'auteur decrit les recherches faites a Chalk River sur la dynamique des reseaux de certains cristaux, y compris le plomb, le sodium, les halogenures alcalins, les semi-conducteurs et d'autres composes complexes. L'analyse des resultats obtenus a basse temperature (environ 100{sup o}K) fournit de nombreux renseignements sur la nature des forces interatomiques. Dans le sodium (metal simple), les forces interatomiques peuvent presque etre derivees d'un potentiel. Dans un metal plus complique, tel que le plomb, on trouve des forces ayant une portee extremement grande et comportant des effets electroniques marques. A des temperatures plus elevees, il se produit des effets anharmoniques tres prononces dans les deux metaux et particulierement dans le plomb. On peut interpreter les resultats obtenus pour les halogenures alcalins en se fondant sur le modele en couche comportant des ions polarisables. Meme aux basses temperatures, les groupes de neutrons correspondant aux modes optiques longitudinaux possedent des largeurs dependant de la temperature, que l'on ne comprend pas encore parfaitement. (author) [Spanish] Los autores pasan revista a las

  18. Determination of Methylmercury Traces in Biological Matrix: Chemical Extraction and Nuclear Quantification with the Neutron Activation Analysis Technique; Determinacion de Trazas de Metilmercurio en Matriz Biologica: Extracion Quimica y Cuantificacion Mediante la Tecnica Nuclear de Analisis por Activacion Neutronica (AANI)

    Energy Technology Data Exchange (ETDEWEB)

    Soldati, A L [Instituto Balseiro, Universidad Nacional de Cuyo, Centro Atomico Bariloche (Argentina)

    2002-07-01

    Mercury is present in the environment as a result of the human and natural activities.The total amount of Hg present in the biosphere has been incremented three times since the industrial era, and now it is affecting in a global sense all the ecosystem.One of the main entrance of Hg in the human diet is the consumption of fish and other marine creatures.Most of the ingested Hg is mono methylmercury (MeHg), which is one of the most toxic forms in which this element could be found because it crosses membranes.Since the toxicity levels are low, the determination of concentrations of total Hg and Me Hg require very careful sampling, sample conditioning and analytical procedures to prevent either losses or contamination, or the degradation of the Hg species.In this work, we implemented a chemical Me Hg extraction procedure, using a ionic exchange resin, with three different types of fish tissue: muscle, liver and hepato pancreas.After Me Hg extraction, the determination and quantification was made by Instrumental Neutron Activation Analysis, by measuring the {sup 197} Au, y el {sup 203} Tl deexcitation s, created through the radioactive decay of the isotopes {sup 197} Hg y {sup 203} Hg.The influence of several parameters on the overall extraction process, such as velocity of passage through the ionic exchange column and the acid concentration used in the extraction was evaluated.Regarding the INAA determinations, a choice was made for the irradiation, decay and counting times, neutron and gamma doses, and the counting geometry The detection limit found for this technique (dry weight) is 140 pg MeHg/g. The Hg contents of the muscle samples were measured with the 279 keV emission of the product of the {sup 202} Hg(n,g){sup 203} Hg reaction, with a recovery of (100 {+-} 13)%. Liver and Hepato pancreas samples were measured with the 77 keV gamma emission of the {sup 197} Hg, checking this result with the 67 y 69 keV X emissions from the same isotope.The liver samples needed

  19. Neutron reflectometry

    DEFF Research Database (Denmark)

    Klösgen-Buchkremer, Beate Maria

    2014-01-01

    of desired information. In the course, an introduction into the method and an overview on selected instruments at large scale facilities will be presented. Examples will be given that illustrate the potential of the method, mostly based on organic films. Results from the investigation of layered films......Neutron (and X-ray) reflectometry constitute complementary interfacially sensitive techniques that open access to studying the structure within thin films of both soft and hard condensed matter. Film thickness starts oxide surfaces on bulk substrates, proceeding to (pauci-)molecular layers and up...... films or films with magnetic properties. The reason is the peculiar property of neutron light since the mass of a neutron is close to the one of a proton, and since it bears a magnetic moment. The optical properties of matter, when interacting with neutrons, are described by a refractive index...

  20. Neutron scattering

    International Nuclear Information System (INIS)

    Furrer, A.

    1993-01-01

    This report contains the text of 16 lectures given at the Summer School and the report on a panel discussion entitled ''the relative merits and complementarities of x-rays, synchrotron radiation, steady- and pulsed neutron sources''. figs., tabs., refs

  1. Neutron storage

    International Nuclear Information System (INIS)

    Strelkov, A.V.

    2004-01-01

    The report is devoted to neutron storage (NS) and describes the history of experiments on the NS development. Great attention is paid to ultracold neutron (UCN) storage. The experiments on the UCN generation, transport, spectroscopy, storage and detection are described. Experiments on searching the UCN electric-dipole moment and electric charge are continued. Possible using of UCN for studying the nanoparticles is discussed [ru

  2. Neutron radiography

    International Nuclear Information System (INIS)

    Bayon, G.

    1989-01-01

    Neutronography or neutron radiography, a non-destructive test method which is similar in its principle to conventional X-ray photography, presently occupies a marginal position among non-destructive test methods (NDT) (no source of suitable performance or cost). Neutron radiography associated with the ORPHEE reactor permits industrial testing; it can very quickly meet a cost requirement comparable to that of conventional test methods. In 1988, 2500 parts were tested on this unit [fr

  3. Study on the mercury evolution in a laboratory multi specific aquatic system by using instrumental neutron activation analysis; Estudio de la evolucion del mercurio en un sistema acuatico de laboratorio multiespecifico utilizando analisis por activacion neutronica instrumental

    Energy Technology Data Exchange (ETDEWEB)

    Bubach, Debora; Guevara, Sergio Ribeiro; Arribere, Maria A. [Comision Nacional de Energia Atomica, San Carlos de Bariloche (Argentina). Centro Atomico Bariloche. Lab. de Analisis por Activacion Nautronica; Pechen de d`Angelo, Ana; Ferrari, Ana; Venturino, Andres [Universidad Nacional del Comahue, Neuquen (Argentina). Facultad de Ingenieria

    1999-11-01

    A preliminary study on the evolution of mercury in the organisms of a laboratory multi specific aquatic system was performed using Instrumental Neutron Activation Analysis (INAA). Some of the possible effects of mercury toxicity were monitored by analyzing early biochemical indicators. The system consisted of an aquarium with bed sediments, aquatic macrophytes (Myriophyllum sp.), bivalves (Diplodom sp.) and exotic fish, simulating a long term contamination situation of unknown causes, where the sediments are the contaminant reservoir. Samples of the abiotic components of the system were analyzed at the beginning of the experiment, and again when the organisms were sampled. Fish carcass, kidney and liver samples, bivalve hepatopancreas, and whole macrophytes were extracted ana analyzed for mercury and other elements by INAA at the beginning of the experiment, and after 48 and 96 hours. Since some crustal elements such as Sc and La were detected in the hepatopancreas and macrophyte samples, enrichment factors for mercury, with respect to the <63 {mu}m sediment fraction, were computed to discriminate the metabolized Hg content from that associated to the particulate. The hepatopancreas index, some indicators of oxidative stress ({gamma}-Glutamyl-cysteinyl-glycine content and lipid peroxidation) and brain acetilcolinesterasa were measured as early indicators of toxicity. (author) 23 refs., 4 tabs.

  4. Neutron detector

    International Nuclear Information System (INIS)

    Endo, Hiroshi.

    1993-01-01

    The device of the present invention detects neutrons in a reactor container under a high temperature and reduces the noise level in an FBR type reactor. That is, the detection section comprises a high heat resistant vessel containing a scintillator therein for detecting neutrons. Neutron signals sent from the detection section are inputted to a neutron measuring section by way of a signal transmission section. The detection section is disposed at the inside of the reactor container. Further, the signal transmission section is connected optically to the detection section. With such a constitution, since the detection section comprising the high temperature resistant vessel is disposed at the inside of the reactor container, neutron fluxes can be detected and measured at high sensitivity even under a high temperature circumstance. Since the signal transmission section is optically connected to the detection section, influence of radiation rays upon transmission of the neutron detection signals can be reduced. Accordingly, the noise level can be kept low. (I.S.)

  5. Neutron Scattering

    International Nuclear Information System (INIS)

    Fayer, Michael J.; Gee, Glendon W.

    2005-01-01

    The neutron probe is a standard tool for measuring soil water content. This article provides an overview of the underlying theory, describes the methodology for its calibration and use, discusses example applications, and identifies the safety issues. Soil water makes land-based life possible by satisfying plant water requirements, serving as a medium for nutrient movement to plant roots and nutrient cycling, and controlling the fate and transport of contaminants in the soil environment. Therefore, a successful understanding of the dynamics of plant growth, nutrient cycling, and contaminant behavior in the soil requires knowledge of the soil water content as well as its spatial and temporal variability. After more than 50 years, neutron probes remain the most reliable tool available for field monitoring of soil water content. Neutron probes provide integrated measurements over relatively large volumes of soil and, with proper access, allow for repeated sampling of the subsurface at the same locations. The limitations of neutron probes include costly and time-consuming manual operation, lack of data automation, and costly regulatory requirements. As more non-radioactive systems for soil water monitoring are developed to provide automated profiling capabilities, neutron-probe usage will likely decrease. Until then, neutron probes will continue to be a standard for reliable measurements of field water contents in soils around the globe

  6. Neutron-neutron probe for uranium exploration

    International Nuclear Information System (INIS)

    Smith, R.C.

    1979-01-01

    A neutron activation probe for assaying the amount of fissionable isotopes in an ore body is described which comprises a casing which is movable through a borehole in the ore body, a neutron source and a number of delayed neutron detectors arranged colinearly in the casing below the neutron source for detecting delayed neutrons

  7. Blood concentrations of ions and metals in amateur and elite runners using neutron activation analyses; Concentracoes de ions e metais em sangue de atletas amadores e de elite usando analise por ativacao neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Luciana Kovacs dos

    2012-07-01

    In this study Br, Ca, Cl, Fe, I, K, Mg, Na, S and Zn concentration were investigated in blood of Brazilian athletes (endurance) using Neutron Activation Analyses technique (NAA). The blood samples were collected from male amateur athletes (AR) and male and female elite athletes (ER), ranging from 18 to 36 year old. The blood samples were collected at the LABEX/UNICAMP and they were irradiated in the nuclear reactor IEA-R1 at IPEN (Sao Paulo, Brazil). The range (at rest) established for AR and ER were compared with the control group (CG), subjects of same gender and age but not involved with physical activities, and showed significant differences for Ca (51 - 439 mgL{sup -1} for CG, 162 - 410 mgL{sup -1} for AR and 64 - 152 mgL{sup -1} for ER) and Br (7.4 - 30.6 mgL{sup -1} for CG, 4.0 - 9.6 mgL{sup -1} for AR and 1.9 - 3.5 mgL{sup -1} for ER), suggesting that a strong dependency of these limits in function of adopted physical training exists. We also performed a systematic investigation for the AR before, during and after the exercise program. These data can be considered for the preparation of a balanced diet, for evaluating the performance of the athletes during the period of competition preparation as well as contributing for proposing new protocols of clinical evaluation not reported in the literature yet. (author)

  8. Administrative Co-ordination of Fissile Material Management and Accounting in the U.K.A.E.A; Coordination Administrative de la Gestion et de la Comptabilite des Matieres Fissiles dans les Etabussements de l'Autorite de l'Energie Atomique du Royaume-Uni; Administrativnaya koordinatsiya kontrolya i ucheta delyashchikhsya materialov v upravlenii po atomnoj ehnergii soedinennogo korolevstva; Coordinacion Administrativa de la Gestion y la Contabilidad de Materiales Fisionables en la Comision de Energia Atomica del Reino Unido

    Energy Technology Data Exchange (ETDEWEB)

    Hood, St. C.C. [United Kingdom Atomic Energy Authority, London (United Kingdom)

    1966-02-15

    mettre au point des procedures et des methodes permettant d'assurer que les matieres sont utilisees de facon economique et renvoyees rapidement. Chaque groupe dispose d'une assez large autonomie en ce qui concerne l'utilisation courante des matieres fissiles. Le systeme administratif precedemment decrit permet aux savants et ingenieurs de l'Autorite, ainsi qu'aux comptables et administrateurs charges de resoudre les problemes relatifs aux matieres fissiles, de travailler collectivement dans un cadre commun en ayant a etablir un minimum de documents. Le memoire est illustre par un diagramme simplifie indiquant les principaux circuits d'operations concernant des matieres fissiles destinees a des fins civiles et traitees dans les etablissements de l'Autorite au cours de l'annee se terminant le 31 mars 1965. (author) [Spanish] La Comision de Energfa Atomica del Reino Unido suministra y consume materiales fisionables: por una parte, tiene a su cargo la produccion, la distribucion , el reciclado y la regeneracion de dichos materiales y, por otra, los necesita para reactores de potencia, prototipos, reactores de ensayo de materiales, instalaciones de potencia cero y proyectos de desarrollo de nuevos combustibles; los utiliza tambien, en cantidades menores, para otros fines experimentales y de investigacion. En lo que respecta a esas actividades, la responsabilidad ejecutiva recae en los cuatro Grupos por mediacion de los cuales la Comision desempena sus funciones. Se ha encontrado conveniente someter todas las actividades mencionadas a la fiscalizacion de comites mixtos de estos Grupos, con una secretaria comun. Dichos comites: a) estudian todos los proyectos y propuestas que requieren el empleo de cantidades importantes de materiales fisionables (plutonio, uranio enriquecido, etc., con exclusion del uranio natural y del uranio empobrecido en {sup 235}U) teniendo en cuenta los suministros que durante un periodo de varios anos se espera recibir de todas las fuentes - produccion

  9. Determination of heavy metals and other elements in sediments from Sepetiba Bay (RJ, Brazil) by neutron activation analysis; Determinacao de metais pesados e outros elementos em sedimentos da Baia de Sepetiba (RJ) por ativacao neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Pellegatti, Fabio

    2000-07-01

    Sepetiba Bay, located about 60 km south of the city of Rio de Janeiro, Brazil, is one of the most important fishery areas in the State of Rio de Janeiro. A large harbor brought up a lot of industrial investment in that area. Since the 1970's, the Sepetiba region has undergone fast industrial expansion, leading to high levels of pollution by metals. For the last two decades, an industrial park composed of about 400 industrial plants, basically metallurgical, was established in the Sepetiba Bay basin, releasing its industrial waste either straight into the bay or through local rivers. Metal contamination in the bay for some metals, such as Zn, has already exceeded acceptable levels. Many authors have studied the distribution and behavior of heavy metals and another elements in the bay, but only few elements have been focused (Cd, Cr, Cu, Fe, Mn, Ni, Pb and Zn). This is probably due to the fact that the analytical technique most employed has been atomic absorption spectrometry, which is not a multi-elemental technique. In this work, Instrumental Neutron Activation Analysis (INAA) was applied to the determination of the elements As, Ba, Br, Ce, Co, Cr, Cs, Eu, Fe, Hf, La, Lu, Nd, Rb, Sc, Sm, Ta, Tb, Th, U, Yb and Zn in 28 bottom sediment samples and four sediment cores from Sepetiba Bay. The elements Co, Cr, Cs, Fe, Sc, Ta and Zn presented similar behavior in the bottom sediments, showing higher concentration along the Northern coast of the bay, where most of the fluvial water flows out to the bay. The contamination of Sepetiba Bay was also assessed by the analysis of four sediment cores. Two of them were sampled in the Eastern part of the bay, where the industrial park is located, whereas the other two were sampled in the Western part of the bay, a more preserved region. For each region, two cores were sampled within the mangrove trees and the others at the edge of the tidal flat. The results showed that, the sediments displayed higher metal concentration within

  10. Determination of {sup 60} Co by means of Neutron Activation Analysis in the sorption of Co in synthesized porous oxides by the combustion method; Determinacion de {sup 60} Co por medio de AAN en la sorcion de Co en oxidos porosos sintetizados por metodo de combustion

    Energy Technology Data Exchange (ETDEWEB)

    Lugo, V.; Bulbulian, S.; Urena, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: violelugo@yahoo.es

    2005-07-01

    Recently inorganic materials are investigating as sorbent of radioactive pollutants present in water. The inorganic oxides belong to this group of materials. A quick method exists for the obtaining of inorganic oxides, denominated combustion method that could be used to produce porous oxides successfully with good properties for the sorption of radioactive ions. In this investigation, iron oxides, magnesium and zinc were synthesized obtained by the combustion method, comparing them with those synthesized by the calcination method, using two different synthesis temperatures. The obtained solids were characterized by scanning electron microscopy (Sem), by X-ray diffraction (XRD) and by semiquantitative elemental analysis (EDS). After the characterization, the crystalline oxides synthesized by both methods, to temperature of 800 C, were evaluated as sorbents in the removal of Co{sup 2+} ions, through experiments in batch, and using neutron activation analysis, determining the sorption percentage, with this it was concluded that the magnesium oxide produced by combustion it is more effective in the removal of Co{sup 2+} ions than that synthesized by calcination. It was determined the surface area of the magnesium oxides, obtaining a surface area greater for the synthesized oxide by combustion method. (Author)

  11. neutron radiography

    International Nuclear Information System (INIS)

    Barton, J.P.

    1993-01-01

    Neutron radiography (or radiology) is a diverse filed that uses neutrons of various energies, subthermal, thermal, epithermal or fast in either steady state or pulsed mode to examine objects for industrial, medical, or other purposes, both microscopic and macroscopic. The applications include engineering design, biological studies, nondestructive inspection and materials evaluation. In the past decade, over 100 different centers in some 30 countries have published reports of pioneering activities using reactors, accelerators and isotopic neutron sources. While film transparency and electronic video are most common imaging methods for static or in motion objects respectively, there are other important data gathering techniques, including track etch, digital gauging and computed tomography. A survey of the world-wide progress shows the field to be gaining steadily in its diversity, its sophistication and its importance. (author)

  12. NEUTRONIC REACTOR

    Science.gov (United States)

    Wigner, E.P.; Weinberg, A.W.; Young, G.J.

    1958-04-15

    A nuclear reactor which uses uranium in the form of elongated tubes as fuel elements and liquid as a coolant is described. Elongated tubular uranium bodies are vertically disposed in an efficient neutron slowing agent, such as graphite, for example, to form a lattice structure which is disposed between upper and lower coolant tanks. Fluid coolant tubes extend through the uranium bodies and communicate with the upper and lower tanks and serve to convey the coolant through the uranium body. The reactor is also provided with means for circulating the cooling fluid through the coolant tanks and coolant tubes, suitable neutron and gnmma ray shields, and control means.

  13. Neutron dosimeter

    International Nuclear Information System (INIS)

    Bartko, J.; Schoch, K.F. Jr.; Congedo, T.V.; Anderson, S.L. Jr.

    1989-01-01

    This patent describes a nuclear reactor. It comprises a reactor core; a thermal shield surrounding the reactor core; a pressure vessel surrounding the thermal shield; a neutron dosimeter positioned outside of the thermal shield, the neutron dosimeter comprising a layer of fissile material and a second layer made of a material having an electrical conductivity which permanently varies as a function of its cumulative ion radiation dose; and means, outside the pressure vessel and electrically connected to the layer of second material, for measuring electrical conductivity of the layer of second material

  14. Quantitative neutron radiography using neutron absorbing honeycomb

    International Nuclear Information System (INIS)

    Tamaki, Masayoshi; Oda, Masahiro; Takahashi, Kenji; Ohkubo, Kohei; Tasaka, Kanji; Tsuruno, Akira; Matsubayashi, Masahito.

    1993-01-01

    This investigation concerns quantitative neutron radiography and computed tomography by using a neutron absorbing honeycomb collimator. By setting the neutron absorbing honeycomb collimator between object and imaging system, neutrons scattered in the object were absorbed by the honeycomb material and eliminated before coming to the imaging system, but the neutrons which were transmitted the object without interaction could reach the imaging system. The image by purely transmitted neutrons gives the quantitative information. Two honeycombs were prepared with coating of boron nitride and gadolinium oxide and evaluated for the quantitative application. The relation between the neutron total cross section and the attenuation coefficient confirmed that they were in a fairly good agreement. Application to quantitative computed tomography was also successfully conducted. The new neutron radiography method using the neutron-absorbing honeycomb collimator for the elimination of the scattered neutrons improved remarkably the quantitativeness of the neutron radiography and computed tomography. (author)

  15. Neutronics of pulsed spallation neutron sources

    CERN Document Server

    Watanabe, N

    2003-01-01

    Various topics and issues on the neutronics of pulsed spallation neutron sources, mainly for neutron scattering experiments, are reviewed to give a wide circle of readers a better understanding of these sources in order to achieve a high neutronic performance. Starting from what neutrons are needed, what the spallation reaction is and how to produce slow-neutrons more efficiently, the outline of the target and moderator neutronics are explained. Various efforts with some new concepts or ideas have already been devoted to obtaining the highest possible slow-neutron intensity with desired pulse characteristics. This paper also reviews the recent progress of such efforts, mainly focused on moderator neutronics, since moderators are the final devices of a neutron source, which determine the source performance. Various governing parameters for neutron-pulse characteristics such as material issues, geometrical parameters (shape and dimensions), the target-moderator coupling scheme, the ortho-para-hydrogen ratio, po...

  16. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    The method of operating a water-cooled neutronic reactor having a graphite moderator is described which comprises flowing a gaseous mixture of carbon dioxide and helium, in which the helium comprises 40--60 volume percent of the mixture, in contact with the graphite moderator. 2 claims, 4 figures

  17. Neutron reflectivity

    Directory of Open Access Journals (Sweden)

    Cousin Fabrice

    2015-01-01

    Full Text Available The specular neutron reflectivity is a technique enabling the measurement of neutron scattering length density profile perpendicular to the plane of a surface or an interface, and thereby the profile of chemical composition. The characteristic sizes that are probed range from around 5 Å up 5000 Å. It is a scattering technique that averages information on the entire surface and it is therefore not possible to obtain information within the plane of the interface. The specific properties of neutrons (possibility of tuning the contrast by isotopic substitution, sensitivity to magnetism, negligible absorption, low energy of the incident neutrons makes it particularly interesting in the fields of soft matter, biophysics and magnetic thin films. This course is a basic introduction to the technique and does not address the magnetic reflectivity. It is composed of three parts describing respectively its principle and its formalism, the experimental aspects of the method (spectrometers, samples and two examples related to the materials for energy.

  18. Methods for absorbing neutrons

    Science.gov (United States)

    Guillen, Donna P [Idaho Falls, ID; Longhurst, Glen R [Idaho Falls, ID; Porter, Douglas L [Idaho Falls, ID; Parry, James R [Idaho Falls, ID

    2012-07-24

    A conduction cooled neutron absorber may include a metal matrix composite that comprises a metal having a thermal neutron cross-section of at least about 50 barns and a metal having a thermal conductivity of at least about 1 W/cmK. Apparatus for providing a neutron flux having a high fast-to-thermal neutron ratio may include a source of neutrons that produces fast neutrons and thermal neutrons. A neutron absorber positioned adjacent the neutron source absorbs at least some of the thermal neutrons so that a region adjacent the neutron absorber has a fast-to-thermal neutron ratio of at least about 15. A coolant in thermal contact with the neutron absorber removes heat from the neutron absorber.

  19. A utilização da difração de neutrões na determinação do perfil de tensões residuais em revestimentos por soldadura The use of neutron diffraction for the determination of the in-depth residual stresses profile in weld coatings

    Directory of Open Access Journals (Sweden)

    Maria José Marques

    2013-06-01

    Full Text Available A técnica de difração de neutrões é usada neste artigo para estudar amostras ferríticas, revestidas comaços inoxidáveisausteníticos através de soldadura por arco submerso. Este procedimento é frequentemente usado no fabrico de equipamentos de processo para as indústrias química e nuclear, por facilidade de execução e razões económicas. A principal desvantagem deste processo de revestimento é a fissuração que frequentemente ocorre na interface material base/soldadura, potenciada pela presença de tensões residuais resultantes da operação de soldadura, a qual pode ser minimizada com a realização de tratamentos térmicos de relaxação de tensões. As amostras foram produzidas a partir de placas em aço ao carbono, tendo uma das superfícies sido revestida com dois tipos de aço inoxidável. Para a primeira camada foi usado um elétrodo EN 12072 - S 23 12 2 L e para a segunda e a terceira camadas foi usado um elétrodo EN 12072 - S 19 12 3 L. Após a soldadura, as amostras foram submetidas a um tratamento térmico de relaxação de tensões, durante 1 hora, à temperatura de 620ºC. Os perfis de tensões residuais obtidos por difração de neutrões evidenciam a relaxação de tensões residuais após o tratamento térmico realizado. A técnica de difração de neutrões revelou-se muito adequada na avaliação de tensões residuais neste tipo de ligações.The neutron diffraction is a non-destructive technique, particularly suitable for the analysis of residual stress fields in welds. The technique is used in this article to study ferritic samples, coated by submerged arc welding using stainless steel filler metals. This procedure is often used for manufacturing process equipment for chemical and nuclear industries, for ease of implementation and economic reasons. The main disadvantage of that processes is the cracking phenomenon that often occurs at the interface between the base material and coatings, which can be

  20. A study on copper and zinc effects in the growth of Aechmea blanchetiana (Baker) L.B. Smith seedlings cultivated in vitro. Application of neutron activation analysis; Estudo sobre os efeitos do cobre e zinco no crescimento da plantula de Aechmea blanchetiana (Baker) L.B. Smith cultivada in vitro. Aplicacao da analise por ativacao com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Zampieri, Maria Cristina Tessari

    2010-07-01

    Metals are components of the biosphere, occurring naturally in soil and plants, but as a result of human actions, their levels have been greatly increased, depending on the region. Copper (Cu) and zinc (Zn) are essential for the growth and development of plants, however if in excess become toxic. The aim of this study was to evaluate the potential of plants to absorb Cu and Zn and what effects they cause in seedlings cultivated in vitro. The results of this study may contribute primarily in agricultural and environmental research. The plant investigated was the Aechmea blanchetiana species of the Bromeliaceae family. It is a terrestrial or epiphytic species used as an ornamental plant. The cultivation of seedlings for this study and their exposure to different concentrations of Cu and Zn were performed at the Institute of Botany (IBt) of Sao Paulo. After seed germination, the seedlings were transferred for growth in a culture media containing different concentrations of Cu or Zn. After this period of in vitro cultivation, the seedlings were analyzed for morphometry, anatomy and by neutron activation analysis. Quality control of the results from neutron activation analysis was carried out by the analysis of certified reference materials. The data obtained showed good precision and accuracy for several elements determined. The highest concentrations of Cu used in the exposure were those that caused major structural changes in morphometric and anatomical parameters, however for the Zn no significant differences were verified for most parameters. The A. blanchetiana proved to be a bioaccumulator species of Zn, absorbing high levels of this element in the aerial parts and roots. (author)

  1. Determination of elementary composition of medicinal plants by Neutron Activation Analysis method; Determinação da composição elementar de plantas medicinais pelo método de análise por ativação com neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Takamoto, Árissa; Saiki, Mitiko, E-mail: arissa.takamoto@gmail.com, E-mail: mitiko@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    The analyzes of medicinal plants are of great interest for the study of the correlation between elements present in them with their therapeutic activities, as well as to identify the toxic elements harmful to health human. In the work, applying the method of analysis by activation with neutrons (NAA), the medicinal plants: Aloe vera (Babosa), Morus nigra sp. (Amoreira) and Moringa oleifera (Moringa) were analysed. The samples were collected in different locations and purchased in a natural products store. The preparation consisted in the cleaning, drying and milling of the leaves. Aliquots of the samples were irradiated with synthetic elements over a period of 16 h and under thermal neutron flux of 5 x 1012 n cm{sup -2} s{sup -1} of the nuclear reactor IEAR-1. The gamma-induced activities were measured on a gamma-ray spectrometer coupled to a detector high resolution. The radioisotopes formed were identified by half-life and energy of the gamma rays and the concentrations of the elements were calculated by the comparative method. The results of the certified reference materials INCT-TL-1 Tea Leaves and INCT-MPH-2 Mixed Polish Herbs showed good precision and accuracy. In the analyzed plants, toxic elements such as Cu and Cd were not detected. Already the As and Sb were detected, but at very low concentrations, on the order of ng g{sup -1}. By NAA method it was possible to determine the concentration of elements As, Br, Ca, Co, Cr, Cs, Fe, K, La, Na, Rb, Sb, Sc and Zn. Results obtained in this work demonstrated the feasibility of applying NAA in the study of medicinal plants.

  2. Neutron stars as cosmic neutron matter laboratories

    International Nuclear Information System (INIS)

    Pines, D.

    1986-01-01

    Recent developments which have radically changed our understanding of the dynamics of neutron star superfluids and the free precession of neutron stars are summarized, and the extent to which neutron stars are cosmic neutron matter laboratories is discussed. 17 refs., 1 tab

  3. Basic of Neutron NDA

    Energy Technology Data Exchange (ETDEWEB)

    Trahan, Alexis Chanel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-09-15

    The objectives of this presentation are to introduce the basic physics of neutron production, interactions and detection; identify the processes that generate neutrons; explain the most common neutron mechanism, spontaneous and induced fission and (a,n) reactions; describe the properties of neutron from different sources; recognize advantages of neutron measurements techniques; recognize common neutrons interactions; explain neutron cross section measurements; describe the fundamental of 3He detector function and designs; and differentiate between passive and active assay techniques.

  4. Radioprotective agents to reduce BNCT (Boron Neutron Capture Therapy) induced mucositis in the hamster cheek pouch; Agentes radioprotectores para reducir la mucositis inducida por la terapia por captura neutrónica en boro (BNCT) en la bolsa de la mejilla del hámster

    Energy Technology Data Exchange (ETDEWEB)

    Monti Hughes, A. [Dpto. de Radiobiología, Gerencia de Química Nuclear y Ciencias de la Salud, GAATEN, Comisión Nacional de Energía Atómica (CNEA) (Argentina); Pozzi, E. C.C. [Gerencia de Reactores de Investigación y Producción, GAATEN, CNEA (Argentina); Thorp, S., E-mail: andrea.monti@cnea.gov.ar [Sub-Gerencia Instrumentación y Control, GAEN, CNEA(Argentina)

    2013-07-01

    Introduction: BNCT is based on the capture reaction between boron, selectively targeted to tumor tissue, and thermal neutrons which gives rise to lethal, short-range high linear energy transfer particles that selectively damage tumor tissue, sparing normal tissue. We previously evidenced a remarkable therapeutic success of BNCT mediated by boronophenylalanine (BPA) in the hamster cheek pouch oral cancer and pre cancer model. Despite therapeutic efficacy, mucositis induced in premalignant tissue was dose limiting and favored, in some cases, tumor development. In a clinical scenario, oral mucositis limits the dose administered to head and neck tumors. Aim: Our aim was to evaluate the effect of the administration of different radioprotective agents, seeking to reduce BNCT-induced mucositis to acceptable levels in dose-limiting premalignant tissue; without compromising therapeutic effect evaluated as inhibition on tumor development in premalignant tissue; without systemic or local side effects; and without negative effects on the biodistribution of the boron compound used for treatment. Materials and methods: Cancerized hamsters with DMBA (dimethylbenzanthracene) were treated with BPA-BNCT 5 Gy total absorbed dose to premalignant tissue, at the RA-3 Nuclear Reactor, divided into different groups: 1-treated with FLUNIXIN; 2- ATORVASTATIN; 3-THALIDOMIDE; 4-HISTAMINE (two concentrations: Low -1 mg/ml- and High -5 mg/ml-); 5-JNJ7777120; 6-JNJ10191584; 7-SALINE (vehicle). Cancerized animals without any treatment (neither BNCT nor radioprotective therapy) were also analyzed. We followed the animals during one month and evaluated the percentage of animals with unacceptable/severe mucositis, clinical status and percentage of animals with new tumors post treatment. We also performed a preliminary biodistribution study of BPA + Histamine “low” concentration to evaluate the potential effect of the radioprotector on BPA biodistribution. Results: Histamine

  5. Neutron scattering. Lectures

    International Nuclear Information System (INIS)

    Brueckel, Thomas; Heger, Gernot; Richter, Dieter; Roth, Georg; Zorn, Reiner

    2013-01-01

    The following topics are dealt with: Neutron sources, symmetry of crystals, nanostructures investigated by small-angle neutron scattering, structure of macromolecules, spin dependent and magnetic scattering, structural analysis, neutron reflectometry, magnetic nanostructures, inelastic neutron scattering, strongly correlated electrons, polymer dynamics, applications of neutron scattering. (HSI)

  6. Neutron scattering. Lectures

    International Nuclear Information System (INIS)

    Brueckel, Thomas; Heger, Gernot; Richter, Dieter; Roth, Georg; Zorn, Reiner

    2012-01-01

    The following topics are dealt with: Neutron scattering in contemporary research, neutron sources, symmetry of crystals, diffraction, nanostructures investigated by small-angle neutron scattering, the structure of macromolecules, spin dependent and magnetic scattering, structural analysis, neutron reflectometry, magnetic nanostructures, inelastic scattering, strongly correlated electrons, dynamics of macromolecules, applications of neutron scattering. (HSI)

  7. Pulsed neutron generator

    International Nuclear Information System (INIS)

    Bespalov, D.F.; Bykovskii, Yu.A.; Vergun, I.I.; Kozlovskii, K.I.; Kozyrev, Yu.P.; Leonov, R.K.; Simagin, B.I.; Tsybin, A.S.; Shikanov, A.Ie.

    1986-03-01

    The paper describes a new device for generating pulsed neutron fields, utilized in nuclear geophysics for carrying out pulsed neutron logging and activation analysis under field conditions. The invention employs a sealed-off neutron tube with a laser ion source which increases neutron yield to the level of 10 neutrons per second or higher. 2 refs., 1 fig

  8. Celulitis por citomegalovirus

    Directory of Open Access Journals (Sweden)

    A. Ruiz Lascano

    2002-12-01

    Full Text Available Las lesiones cutáneas por citomegalovirus (CMV son infrecuentes y a menudo una manifestación tardía de una enfermedad sistémica, que generalmente anuncia un curso fatal. Comunicamos un caso de celulitis por CMV: una mujer de 70 años con trasplante renal efectuado 1 mes antes de la consulta, terapia inmunosupresora con ciclosporina A y metilprednisona. La paciente ingresó por fiebre, dolor e impotencia funcional en pierna derecha. Comprobamos la existencia de una placa de 8 por 4 cm eritematoedematosa. La tratamos con antibióticos sin mejoría, por lo que realizamos un estudio histopatológico de piel que mostró cambios citopáticos compatibles con infección por CMV. Los cultivos bacteriológicos y micológicos fueron negativos. La inmunohistoquímica específica para CMV y el estudio de reacción en cadena de la polimerasa (PCR de la biopsia de piel fueron positivas, al igual que la antigenemia. El tratamiento con ganciclovir produjo la mejoría del cuadro clínico. En la literatura revisada no hemos encontrado la celulitis como manifestación de enfermedad cutánea por CMV.

  9. Neutron scattering

    International Nuclear Information System (INIS)

    1991-02-01

    The annual report on hand gives an overview of the research work carried out in the Laboratory for Neutron Scattering (LNS) of the ETH Zuerich in 1990. Using the method of neutron scattering, it is possible to examine in detail the static and dynamic properties of the condensed material. In accordance with the multidisciplined character of the method, the LNS has for years maintained a system of intensive co-operation with numerous institutes in the areas of biology, chemistry, solid-state physics, crystallography and materials research. In 1990 over 100 scientists from more than 40 research groups both at home and abroad took part in the experiments. It was again a pleasure to see the number of graduate students present, who were studying for a doctorate and who could be introduced into the neutron scattering during their stay at the LNS and thus were in the position to touch on central ways of looking at a problem in their dissertation using this modern experimental method of solid-state research. In addition to the numerous and interesting ways of formulating the questions to explain the structure, nowadays the scientific programme increasingly includes particularly topical studies in connection with high temperature-supraconductors and materials research

  10. Neutron radiotherapy

    International Nuclear Information System (INIS)

    Thomas, F.J.

    1987-01-01

    The rationale for the application of neutron radiation for the treatment of malignancies is well established based on radiobiological studies. These factors include the presence of tissue hypoxia, radiation response as a function of cell cycle kinetics, the repair capacity of the malignant cells and the regeneration of malignant cells during a fractionated course of radiation. Despite the constraints under which the clinical trials to date have been conducted, promising results have been obtained. Randomized trials have demonstrated that neutron therapy is the treatment of choice for inoperable salivary gland carcinomas. A randomized trial of the RTOG has demonstrated a probable advantage for neutron radiation in the treatment of advanced prostate carcinomas but is yet to be confirmed. An improvement in local control has also been observed for selected sarcomas. Equivocal or contradictory results have been obtained for squamous cell carcinomas of the head and neck, bronchogenic carcinomas, advanced rectal, transitional cell carcinomas of the bladder and cervical carcinomas. The practical consequences of these radiobiological and clinical observations on the current generation of clinical trials is discussed

  11. Accounting Systems for Heavy Water and Fissionable Materials; Comptabilite de l'Eau Lourde et des Matieres Fissiles; Sistema ucheta tyazheloj vody i delyashchikhsya materialov; Sistemas de Contabilidad para el Agua Pesada y los Materiales Fisionables

    Energy Technology Data Exchange (ETDEWEB)

    Fletcher, G. W.; Reid, H. B.; Jenkinson, W. G. [Atomic Energy of Canada Ltd., Chalk River, ON (Canada)

    1966-02-15

    rapports soumis a l'approbation du comite de gestion sont egalement decrits. Les auteurs fournissent des explications sur le systeme de comptabilite de l'eau lourde qui repose sur les memes principes que le systeme de comptabilite des matieres fissiles. Dans ce cas, on inscrit dans le grand registre de controle le poids d e D{sub 2}O attribue a chacune des 15 sections comptables. La encore, les auteurs exposent les principales methodes comptables et decrivent l'utilisation de la calculatrice. (author) [Spanish] Los autores describen detalladamente los procedimientos de contabilidad e informacion que emplea la Atomic Energy of Canada Limited (AECL) para mantener registros adecuados y ejercer un control eficiente de los suministros de agua pesada y de las existencias de materiales fisionables, y exponen los deberes y las responsabilidades de las personas encargadas de la fiscalizacion. Evaluan estos procedimientos desde el punto de vista de su adaptabilidad a programas de investigacion y de produccion de energia en rapido desarrollo y tratan en particular del empleo de equipo electronico para la sistematizacion de los datos. Un comite administrativo superior vela para que se aplique un sistema adecuado de registro y fiscalizacion de los materiales nucleares. La Seccion de Planeamiento y Control de la Produccion de la Division de Operaciones d e los Laboratorios Nucleares de Chalk River (CRNL) responde ante dicho comite del mantenimiento de los registros y del buen funcionamiento del sistema. En la memoria se exponen detalladamente sus funciones. Para los materiales fisionables, el sistema consta de varias unidades contables, quince de las cuales corresponden a departamentos de la AECL y las demas a industrias y centros de investigacion del Canada- La Seccion de Planeamiento y Control de la Produccion lleva un libro mayor para cada una de las unidades, pero estas contabilizan detalladamente todos los materiales que se hallan bajo su jurisdiccion. En la memoria se exponen a

  12. Spallation Neutron Source (SNS)

    Data.gov (United States)

    Federal Laboratory Consortium — The SNS at Oak Ridge National Laboratory is a next-generation spallation neutron source for neutron scattering that is currently the most powerful neutron source in...

  13. High energy neutron radiography

    International Nuclear Information System (INIS)

    Gavron, A.; Morley, K.; Morris, C.; Seestrom, S.; Ullmann, J.; Yates, G.; Zumbro, J.

    1996-01-01

    High-energy spallation neutron sources are now being considered in the US and elsewhere as a replacement for neutron beams produced by reactors. High-energy and high intensity neutron beams, produced by unmoderated spallation sources, open potential new vistas of neutron radiography. The authors discuss the basic advantages and disadvantages of high-energy neutron radiography, and consider some experimental results obtained at the Weapons Neutron Research (WNR) facility at Los Alamos

  14. Neutron scattering. Lectures

    Energy Technology Data Exchange (ETDEWEB)

    Brueckel, Thomas; Heger, Gernot; Richter, Dieter; Roth, Georg; Zorn, Reiner (eds.)

    2010-07-01

    The following topics are dealt with: Neutron sources, neutron properties and elastic scattering, correlation functions measured by scattering experiments, symmetry of crystals, applications of neutron scattering, polarized-neutron scattering and polarization analysis, structural analysis, magnetic and lattice excitation studied by inelastic neutron scattering, macromolecules and self-assembly, dynamics of macromolecules, correlated electrons in complex transition-metal oxides, surfaces, interfaces, and thin films investigated by neutron reflectometry, nanomagnetism. (HSI)

  15. Neutron scattering. Lectures

    International Nuclear Information System (INIS)

    Brueckel, Thomas; Heger, Gernot; Richter, Dieter; Roth, Georg; Zorn, Reiner

    2010-01-01

    The following topics are dealt with: Neutron sources, neutron properties and elastic scattering, correlation functions measured by scattering experiments, symmetry of crystals, applications of neutron scattering, polarized-neutron scattering and polarization analysis, structural analysis, magnetic and lattice excitation studied by inelastic neutron scattering, macromolecules and self-assembly, dynamics of macromolecules, correlated electrons in complex transition-metal oxides, surfaces, interfaces, and thin films investigated by neutron reflectometry, nanomagnetism. (HSI)

  16. Neutron Therapy Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Neutron Therapy Facility provides a moderate intensity, broad energy spectrum neutron beam that can be used for short term irradiations for radiobiology (cells)...

  17. Calculations of neutron spectra after neutron-neutron scattering

    Energy Technology Data Exchange (ETDEWEB)

    Crawford, B E [Gettysburg College, Box 405, Gettysburg, PA 17325 (United States); Stephenson, S L [Gettysburg College, Box 405, Gettysburg, PA 17325 (United States); Howell, C R [Duke University and Triangle Universities Nuclear Laboratory, Durham, NC 27708-0308 (United States); Mitchell, G E [North Carolina State University, Raleigh, NC 27695-8202 (United States); Tornow, W [Duke University and Triangle Universities Nuclear Laboratory, Durham, NC 27708-0308 (United States); Furman, W I [Joint Institute for Nuclear Research, 141980 Dubna (Russian Federation); Lychagin, E V [Joint Institute for Nuclear Research, 141980 Dubna (Russian Federation); Muzichka, A Yu [Joint Institute for Nuclear Research, 141980 Dubna (Russian Federation); Nekhaev, G V [Joint Institute for Nuclear Research, 141980 Dubna (Russian Federation); Strelkov, A V [Joint Institute for Nuclear Research, 141980 Dubna (Russian Federation); Sharapov, E I [Joint Institute for Nuclear Research, 141980 Dubna (Russian Federation); Shvetsov, V N [Joint Institute for Nuclear Research, 141980 Dubna (Russian Federation)

    2004-09-01

    A direct neutron-neutron scattering length, a{sub nn}, measurement with the goal of 3% accuracy (0.5 fm) is under preparation at the aperiodic pulsed reactor YAGUAR. A direct measurement of a{sub nn} will not only help resolve conflicting results of a{sub nn} by indirect means, but also in comparison to the proton-proton scattering length, a{sub pp}, shed light on the charge-symmetry of the nuclear force. We discuss in detail the analysis of the nn-scattering data in terms of a simple analytical expression. We also discuss calibration measurements using the time-of-flight spectra of neutrons scattered on He and Ar gases and the neutron activation technique. In particular, we calculate the neutron velocity and time-of-flight spectra after scattering neutrons on neutrons and after scattering neutrons on He and Ar atoms for the proposed experimental geometry, using a realistic neutron flux spectrum-Maxwellian plus epithermal tail. The shape of the neutron spectrum after scattering is appreciably different from the initial spectrum, due to collisions between thermal-thermal and thermal-epithermal neutrons. At the same time, the integral over the Maxwellian part of the realistic scattering spectrum differs by only about 6 per cent from that of a pure Maxwellian nn-scattering spectrum.

  18. Study of the spatial dependence of neutronic flow oscillations caused by fluctuations thermohydraulics at the entrance of the core of a reactor PWR; Estudio de la dependencia espacial de las oscilaciones de flujo neutronico causadas por flucturaciones termohidraulicas a la entrada del nucleo de un reactor PWR

    Energy Technology Data Exchange (ETDEWEB)

    Bermejo, J. A.; Lopez, A.; Ortego, A.

    2014-07-01

    It presents a theoretical study on spatial dependence of flow oscillations neutronic caused by thermal hydraulics fluctuations at the entrance of the core of a PWR reactor. To simulate, with SIMULATE code - 3K different fluctuations thermohydraulics at the entrance to the core and the spatial dependence of the oscillations and is analyzed neutronic flow obtained at locations of neutron detectors. the work It is part of the r and d program initiated in CNAT to investigate the phenomenon of the noise neutronic. (Author)

  19. Determinação de elementos minerais e traços por ativação neutrônica, em refeições servidas no restaurante da Faculdade de Saúde Pública/USP Determination of mineral and trace elements by neutron activation analysis, in meals served at the central cafeteria of Faculty of Public Health/USP

    Directory of Open Access Journals (Sweden)

    Déborah I.T. FÁVARO

    2000-08-01

    Full Text Available Dentro do contexto de assegurar à população dietas equilibradas em relação aos elementos essenciais e uma monitoração dos elementos tóxicos, este trabalho teve por objetivo a determinação dos níveis desses elementos, em refeições servidas no restaurante da Faculdade de Saúde Pública/USP freqüentada pelos estudantes universitários e funcionários, durante uma semana. Foram analisadas refeições servidas no almoço. Os alimentos foram recolhidos em bandejas completas em número de 3 por refeição, tomando-se por base as porções servidas, consideradas como análise em duplicata. Foram feitas análises para determinação da composição centesimal das refeições utilizando-se os métodos preconizados pela AOAC. As amostras foram submetidas também a análise multielementar utilizando-se a técnica de análise por ativação neutrônica, onde os seguintes elementos puderam ser determinados: Ba, Br, Ca, Ce, Cl, Co, Cr, Cs, Fe, K, Mg, Mn, Mo, Na, Rb, Sb, Sc, Se e Zn, níveis de m g/g a ng/g. Os resultados de ingestão por refeição obtidos no presente trabalho foram comparados com os valores diários recomendados pelo RDA, WHO e Homem Padrão. Salienta-se em relação aos macronutrientes, uma alta adequação protéica e excesso de lípides em algumas refeições, interferindo no valor calórico total. Dentre as causas de maior variação dos resultados a dieta entre os diferentes dias é a que mais contribui. Em relação à fração fibra alimentar, os valores obtidos foram adequados. Quanto aos micronutrientes, observa-se adequação quanto a Br, Ca, Fe, Mg, Mn, Rb, Se e Zn, entretanto, níveis acima do recomendado para K, Mo, Na, Cl e Cr. Para os elementos Ba, Co, Cs e Sb os níveis de ingestão foram comparados com os dados de ingestão diária para Homem Padrão. Os demais elementos traço determinados como Ce e Sc, observa-se que não existe recomendação, tendo-se observado grandes variações nos valores obtidos para

  20. Electrocardiografo por computadora

    OpenAIRE

    Tinoco Hernandez, Rosanna; Paredes Bejarano, Margarita; Romero Chaglia, Norman; Yapur Auad, Miguel Eduardo

    2009-01-01

    El presente trabajo trata sobrees el diseño y la implementación de un graficador de señales cardiacas por computadora, para lo cual diseñamos un circuito electrónico capaz de recibir la senal analógica proveniente de la actividad electrica del corazón , amplificarla, y luego convertirla en una señal digital para ser procesada por software y finalmente ser graficada, siendo posible así observar la señal cardiaca en el monitor de un computador como un tren de pulsos. Cabe destacar que par...

  1. Neutron matter, symmetry energy and neutron stars

    Energy Technology Data Exchange (ETDEWEB)

    Stefano, Gandolfi [Los Alamos National Laboratory (LANL); Steiner, Andrew W [ORNL

    2016-01-01

    Recent progress in quantum Monte Carlo with modern nucleon-nucleon interactions have enabled the successful description of properties of light nuclei and neutron-rich matter. Of particular interest is the nuclear symmetry energy, the energy cost of creating an isospin asymmetry, and its connection to the structure of neutron stars. Combining these advances with recent observations of neutron star masses and radii gives insight into the equation of state of neutron-rich matter near and above the saturation density. In particular, neutron star radius measurements constrain the derivative of the symmetry energy.

  2. Directional epithermal neutron detector

    International Nuclear Information System (INIS)

    Givens, W.W.; Mills, W.R. Jr.

    1986-01-01

    A borehole tool for epithermal neutron die-away logging of subterranean formations surrounding a borehole is described which consists of: (a) a pulsed source of fast neutrons for irradiating the formations surrounding a borehole, (b) at least one neutron counter for counting epithermal neutrons returning to the borehole from the irradiated formations, (c) a neutron moderating material, (d) an outer thermal neutron shield providing a housing for the counter and the moderating material, (e) an inner thermal neutron shield dividing the housing so as to provide a first compartment bounded by the inner thermal neutron shield and a first portion of the outer thermal neutron shield and a second compartment bounded by the inner thermal neutron shield and a second portion of the outer thermal neutron shield, the counter being positioned within the first compartment and the moderating material being positioned within the second compartment, and (f) means for positioning the borehole tool against one side of the borehole wall and azimuthally orienting the borehole tool such that the first chamber is in juxtaposition with the borehole wall, the formation epithermal neutrons penetrating into the first chamber through the first portion of the outer thermal neutron shield are detected by the neutron counter for die-away measurement, thereby maximizing the directional sensitivty of the neutron counter to formation epithermal neutrons, the borehole fluid epithermal neutrons penetrating into the second chamber through the second chamber through the second portion of the outer thermal neutron shield are largely slowed down and lowered in energy by the moderating material and absorbed by the inner thermal neutron shield before penetrating into the first chamber, thereby minimizing the directional sensitivity of the neutron counter to borehole fluid epithermal neutrons

  3. Powder neutron diffractometers

    International Nuclear Information System (INIS)

    Adib, M.

    2002-01-01

    Basic properties and applications of powder neutron Diffractometers are described for optimum use of the continuous neutron beams. These instruments are equipped with position sensitive detectors, neutron guide tubes, and both high intensity and high resolution modes of operation are possible .The principles of both direct and Fourier reverse time-of-flight neutron Diffractometers are also given

  4. Neutron dosimetry - A review

    Energy Technology Data Exchange (ETDEWEB)

    Baum, J W

    1955-03-29

    This review summarizes information on the following subjects: (1) physical processes of importance in neutron dosimetry; (2) biological effects of neutrons; (3) neutron sources; and (4) instruments and methods used in neutron dosimetry. Also, possible improvements in dosimetry instrumentation are outlined and discussed. (author)

  5. Neutron scattering. Lectures

    Energy Technology Data Exchange (ETDEWEB)

    Brueckel, Thomas; Heger, Gernot; Richter, Dieter; Roth, Georg; Zorn, Reiner [eds.

    2010-07-01

    The following topics are dealt with: Neutron sources, symmetry of crystals, diffraction, nanostructures investigated by small-angle neutron scattering, the structure of macromolecules, spin dependent and magnetic scattering, structural analysis, neutron reflectometry, magnetic nanostructures, inelastic scattering, strongly correlated electrons, dynamics of macromolecules, applications of neutron scattering. (HSI)

  6. Neutron generator control system

    International Nuclear Information System (INIS)

    Peelman, H.E.; Bridges, J.R.

    1981-01-01

    A method is described of controlling the neutron output of a neutron generator tube used in neutron well logging. The system operates by monitoring the target beam current and comparing a function of this current with a reference voltage level to develop a control signal used in a series regulator to control the replenisher current of the neutron generator tube. (U.K.)

  7. Genetic effect of neutrons

    International Nuclear Information System (INIS)

    Luchnik, N.V.; Sevan'kaev, A.V.; Fesenko, Eh.V.

    1984-01-01

    Gene mutations resulting from neutron effect are considered, but attention is focused on chromosome mutations. Dose curves for different energy of neutrons obtained at different objects are obtained which makes it possible to consider RBE of neutrons depending on their energy and radiation dose and to get some information on the neutron effect on heredity

  8. Neutron scattering. Lectures

    International Nuclear Information System (INIS)

    Brueckel, Thomas; Heger, Gernot; Richter, Dieter; Roth, Georg; Zorn, Reiner

    2010-01-01

    The following topics are dealt with: Neutron sources, symmetry of crystals, diffraction, nanostructures investigated by small-angle neutron scattering, the structure of macromolecules, spin dependent and magnetic scattering, structural analysis, neutron reflectometry, magnetic nanostructures, inelastic scattering, strongly correlated electrons, dynamics of macromolecules, applications of neutron scattering. (HSI)

  9. Neutronics of pulsed spallation neutron sources

    International Nuclear Information System (INIS)

    Watanabe, Noboru

    2003-01-01

    Various topics and issues on the neutronics of pulsed spallation neutron sources, mainly for neutron scattering experiments, are reviewed to give a wide circle of readers a better understanding of these sources in order to achieve a high neutronic performance. Starting from what neutrons are needed, what the spallation reaction is and how to produce slow-neutrons more efficiently, the outline of the target and moderator neutronics are explained. Various efforts with some new concepts or ideas have already been devoted to obtaining the highest possible slow-neutron intensity with desired pulse characteristics. This paper also reviews the recent progress of such efforts, mainly focused on moderator neutronics, since moderators are the final devices of a neutron source, which determine the source performance. Various governing parameters for neutron-pulse characteristics such as material issues, geometrical parameters (shape and dimensions), the target-moderator coupling scheme, the ortho-para-hydrogen ratio, poisoning, etc are discussed, aiming at a high performance pulsed spallation source

  10. Neutron shieldings

    International Nuclear Information System (INIS)

    Tarutani, Kohei

    1979-01-01

    Purpose: To decrease the stresses resulted by the core bendings to the base of an entrance nozzle. Constitution: Three types of round shielding rods of different diameter are arranged in a hexagonal tube. The hexagonal tube is provided with several spacer pads receiving the loads from the core constrain mechanism at its outer circumference, a handling head for a fuel exchanger at its top and an entrance nozzle for self-holding the neutron shieldings and flowing heat-removing coolants at its bottom. The diameters for R 1 , R 2 and R 3 for the round shielding rods are designed as: 0.1 R 1 2 1 and 0.2 R 1 2 1 . Since a plurality of shielding rods of small diameter are provided, soft structure are obtained and a plurality of coolant paths are formed. (Furukawa, Y.)

  11. Comparison of the Economic Aspects of the Treatment and Storage of Fission Products from Installations Processing Irradiated Natural Uranium; Aspects Economiques Compares du Traitement et du Stockage des Produits de Fission Issus des Usines de Traitement de l'Uranium Naturel Irradie; Sravnitel'nye ehkonomicheskie aspekty obrabotki i khraneniya produktov deleniya, poluchaemykh na zavodakh po pererabotke obluchennogo prirodnogo urana; Aspectos Economicos Comparados del Tratamiento y del Almacenamiento de los Productos de Fision que Salen de las Plantas de Tratamiento de Uranio Natural Irradiado

    Energy Technology Data Exchange (ETDEWEB)

    Thiriet, L.; Lesur, P.; Giraud, R. [Commissariat a l' Energie Atomique, Paris (France); Wanlin, J. [Societe Saint-Gobain Techniques Nouvelles, Paris (France)

    1966-02-15

    reservoirs pouvant etre construits, et on determine la taille et la cadence optimales de leur mise en service, compte tenu des caracteristiques des produits de fission a stocker et pour diverses capacites de l'usine de traitement de l'uranium naturel irradie. Ils montrent que, si le cout de stockage depend des hypotheses faites sur la duree de vie des installations, le taux d'interet, les frais d'exploitation, le choix de la politique optimale par contre (tailles et cadences de mise en service) est independant de ces hypotheses et n'est lie qu'a la loi de variation du cout des reservoirs selon leur taille. On obtient ainsi le cout optimise de stockage indefini de ces effluents. Dans une troisieme partie, les auteurs comparent a cette solution du stockage indefini d'autres politiques possibles de gestion des produits de fission: vitrification et separation du Cs et du Sr. Ils situent economiquement ces diverses alternatives et esquissent des solutions possibles a long terme. (author) [Spanish] Despues de recordar las principales practicas administrativas que suelen aplicarse a los productos de fision, los autores exponen sucintamente las caracteristicas tecnicas esenciales de las instalaciones de almacenamiento en acero inoxidable (en medio acido) utilizadas en Francia y analizan la estructura de sus costos. Muestran hasta que punto esos costos dependen de la radiactividad de las soluciones almacenadas y del calor que desprenden. En la segunda parte de la memoria se examina el costo del almacenamiento segun las dimensiones de los depositos que pueden construirse, se determinan las dimensiones optimas de estos depositos y se indica el ritmo mas conveniente para su puesta en servicio teniendo en cuenta las caracteristicas de los productos de fision que es preciso almacenar y las diversas capacidades de las plantas de tratamiento de uranio natural irradiado. Se demuestra que si bien el costo del almacenamiento depende de algunas hipotesis (duracion de la vida util de las

  12. Miscellaneous neutron techniques

    International Nuclear Information System (INIS)

    Iddings, F.A.

    1976-01-01

    Attention is brought to the less often uses of neutrons in the areas of neutron radiography, well logging, and neutron gaging. Emphasis on neutron radiography points toward the isotopic sensitivity of the method versus the classical bulk applications. Also recognized is the ability of neutron radiography to produce image changes that correspond to thickness and density changes obtained in photon radiography. Similarly, neutron gaging applications center on the measurement of radiography. Similarly, neutron gaging applications center on the measurement of water, oil, or plastics in industrial samples. Well logging extends the neutron gaging to encompass many neutron properties and reactions besides thermalization and capture. Neutron gaging also gives information on organic structure and concentrations of a variety of elements or specific compounds in selected matrices

  13. Nuclear reactor neutron shielding

    Science.gov (United States)

    Speaker, Daniel P; Neeley, Gary W; Inman, James B

    2017-09-12

    A nuclear reactor includes a reactor pressure vessel and a nuclear reactor core comprising fissile material disposed in a lower portion of the reactor pressure vessel. The lower portion of the reactor pressure vessel is disposed in a reactor cavity. An annular neutron stop is located at an elevation above the uppermost elevation of the nuclear reactor core. The annular neutron stop comprises neutron absorbing material filling an annular gap between the reactor pressure vessel and the wall of the reactor cavity. The annular neutron stop may comprise an outer neutron stop ring attached to the wall of the reactor cavity, and an inner neutron stop ring attached to the reactor pressure vessel. An excore instrument guide tube penetrates through the annular neutron stop, and a neutron plug comprising neutron absorbing material is disposed in the tube at the penetration through the neutron stop.

  14. Forecasting the Quantity and Activity of Fission Products in France in Future Years in the Light of Atomic Energy Development; Quantite et Activite des Produits de Fission Obtenus en France dans les Annees a Venir Compte Tenu du Developpement de l'Energie Atomique; 041a 041e 041b 0414 ; Cantidad y Actividad de los Productos de Fision que se Obtendran en Francia en los Anos Venideros, Habida Cuenta del Desarrollo de la Energia Atomica

    Energy Technology Data Exchange (ETDEWEB)

    Guirlet, J.; Lavie, J. M. [Commissariat a l' Energie Atomique, Saclay (France)

    1960-07-01

    With the aid of Wigner and Way's formula it is possible to predict theoretically the activity of the complex mixture of fission products originating in a reactor. Account is taken in the study of prospective nuclear power production in France up to 1975. It is assumed that the uranium stays in the reactor for periods of three and of six months. It is also possible to determine the activity of a given fission product and to calculate its decay time. The substance selected was strontium for an activation period of three months. Each group of curves shows total activity at any moment and the activity of particular fission products over a given period. (author) [French] En utilisant la formule de Wigner et Way, il est possible de prevoir theoriquement l'activite du melange complexe de produits de fission provenant d'une pile. L'etude a ete faite en tenant compte de previsions en ce qui concerne en France la production d'electricite d'origine atomique jusqu'en 1975. On a suppose des temps de sejour en pile de l'uranium de trois mois et de six mois. Il est possible egalement de trouver l'activite d'un produit de fission particulier, et de donner sa decroissance. Le corps choisi est le strontium pour un temps d'activation de trois mois. Chaque ensemble de courbes donne a tout instant l'activite totale, et l'activite propre des produits de fission correspondant a une periode donnee. (author) [Spanish] Empleando la formula de Wigner y Way se puede calcular teoricamente la actividad de la mezcla compleja de productos de fision procedentes de una pila. Para esta memoria se han tenido en cuenta las previsiones de produccion de electricidad nucleoelectrica en Francia hasta 1975. Los autores suponen que el uranio permanece tres o seis meses en la pila y han conseguido determinar la actividad de un producto de fision determinado, asi como su periodo de desintegracion. Han escogido el estroncio, con un tiempo de activacion de 3 meses. Cada conjunto de curvas da la actividad total

  15. Indice por Materias

    Directory of Open Access Journals (Sweden)

    Montoya H Luz Marina

    1982-09-01

    Full Text Available Un índice es una lista de palabras o frases indicadores asociados que permite la ubicación de material al interior de un libro o una publicación, en este caso será por el nombre de la materia.

  16. The representation of neutron polarization

    International Nuclear Information System (INIS)

    Byrne, J.

    1979-01-01

    Neutron beam polarization representation is discussed under the headings; transfer matrices, coherent parity violation for neutrons, neutron spin rotation in helical magnetic fields, polarization and interference. (UK)

  17. Pulsed neutron sources for epithermal neutrons

    International Nuclear Information System (INIS)

    Windsor, C.G.

    1978-01-01

    It is shown how accelerator based neutron sources, giving a fast neutron pulse of short duration compared to the neutron moderation time, promise to open up a new field of epithermal neutron scattering. The three principal methods of fast neutron production: electrons, protons and fission boosters will be compared. Pulsed reactors are less suitable for epithermal neutrons and will only be briefly mentioned. The design principle of the target producing fast neutrons, the moderator and reflector to slow them down to epithermal energies, and the cell with its beam tubes and shielding will all be described with examples taken from the new Harwell electron linac to be commissioned in 1978. A general comparison of pulsed neutron performance with reactors is fraught with difficulties but has been attempted. Calculation of the new pulsed source fluxes and pulse widths is now being performed but we have taken the practical course of basing all comparisons on extrapolations from measurements on the old 1958 Harwell electron linac. Comparisons for time-of-flight and crystal monochromator experiments show reactors to be at their best at long wavelengths, at coarse resolution, and for experiments needing a specific incident wavelength. Even existing pulsed sources are shown to compete with the high flux reactors in experiments where the hot neutron flux and the time-of-flight methods can be best exploited. The sources under construction can open a new field of inelastic neutron scattering based on energy transfer up to an electron volt and beyond

  18. Molecular Dynamics Investigated by Neutron Scattering; Etude de la Dynamique Moleculaire au Moyen de la Diffusion des Neutrons; 0418 0421 0421 041b 0415 0414 041e 0412 0410 041d 0418 0415 041c 041e 041b 0415 041a 0423 041b 042f 0420 041d 041e 0419 0414 0418 041d 0410 041c 0418 041a 0418 0421 041f 041e 041c 041e 0429 042c 042e 0420 0410 0421 0421 0415 042f 041d 0418 042f 041d 0415 0419 0422 0420 041e 041d 041e 0412 ; Estudio de la Dinamica Molecular por Dispersion Neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Janik, J. A. [Institute for Nuclear Physics, Cracow (Poland)

    1965-06-15

    }OClO{sub 4} sobre la base de experimentos de dispersion inelastica de neutrones. Los resultados obtenidos indican que la rotacion del grupo NH4 en el perclorato amonico es libre, incluso a temperaturas tan bajas como la del nitrogeno liquido. En lo que respecta al H{sub 3}OClO{sub 4}, se ha observado una vibracion torsional del grupo H{sub 3}O con una frecuencia de 497 cm{sup -1}. Por tanto, a pesar de la identidad de las redes cristalinas del NH{sub 4}CIO{sub 4} y del H{sub 3}OCIO{sub 4}, la dinamica de los grupos NH{sub 4} es diferente de la de los grupos H{sub 3}O. Los resultados se comparan con los obtenidos por espectroscopia Raman y resonancia magnetica nuclear. Por ultimo, se estudia una serie de sustancias desde el punto de vista de su dinamica molecular. (author) [Russian] Kratko rassmatrivaetsja polozhenie s voprosom o primenimosti teorii Krigera- Nel'kina i teorii Griffinga v otnoshenii gazov. Zatem na osnovanii jeksperimentov s zhidkim metanom kriticheski rassmatrivaetsja vopros o primenimosti koncepcii tenzora massy v otnoshenii molekul v kondensirovannom sostojanii. Ubeditel'nymi dovodami protiv primenenija teorii Krigera-Nel'kina v otnoshenii kondensirovannyh sostojanij javljajutsja: sdvig raspredelenija jenergii nejtronov posle rassejanija v storonu bolee vysokih jenergij i otsutstvie zavisimosti neuprugoj chasti ot ugla rassejanija. Sledujushhie razdely posvjashheny rotacionnoj dinamike ammonievyh grupp v soedinenijah ammonija. Bol'shaja chast' jeksperimental'nogo materiala rassmatrivaetsja v svjazi s galoidami ammonija, ishodja iz rezul'tatov jeksperimentov razlichnyh avtorov. Dlja nekotoryh veshhestv svoboda vrashhenija grupp NH{sub 4} poluchena na osnovanii izmerenija nejtronov, togda kak dlja nekotoryh drugih jeto vrashhenie perehodit v krutil'noe kolebanie. V jetom sluchae chastoty krutil'nyh kolebanij, poluchennye razlichnymi avtorami v rezul'tate izmerenija nejtronov, sravnivalis' s chastotami, poluchennymi s pomoshh'ju infrakrasnoj

  19. Apendicitis por Paracoccidioides brasiliensis

    Directory of Open Access Journals (Sweden)

    Ana Beatriz MUÑOZ URRIBARRI

    2006-01-01

    Full Text Available La paracoccidioidomicosis es la micosis más prevalente en Sudamérica. La forma aguda afecta el sistema fagocítico mononuclear de niños y personas inmunocomprometidas. El compromiso gastrointestinal es frecuente y su patogenia implica diseminación hematógena y linfática. La linfadenomegalia abdominal causa obstrucción intestinal y abdomen agudo. En este artículo damos a conocer el caso de un niño con compromiso gastrointestinal por apendicitis. Este es el primer caso reportado de apendicitis por esta patología. (Rev Med Hered 2006;17:58-60.

  20. Neutron in biology

    Energy Technology Data Exchange (ETDEWEB)

    Niimura, Nobuo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-11-01

    Neutron in biology can provide an experimental method of directly locating relationship of proteins and DNA. However, there are relatively few experimental study of such objects since it takes a lot of time to collect a sufficient number of Bragg reflections and inelastic spectra due to the low flux of neutron illuminating the sample. Since a next generation neutron source of JAERI will be 5MW spallation neutron source and its effective neutron flux will be 10{sup 2} to 10{sup 3} times higher than the one of JRR-3M, neutron in biology will open a completely new world for structural biology. (author)

  1. Layered semiconductor neutron detectors

    Science.gov (United States)

    Mao, Samuel S; Perry, Dale L

    2013-12-10

    Room temperature operating solid state hand held neutron detectors integrate one or more relatively thin layers of a high neutron interaction cross-section element or materials with semiconductor detectors. The high neutron interaction cross-section element (e.g., Gd, B or Li) or materials comprising at least one high neutron interaction cross-section element can be in the form of unstructured layers or micro- or nano-structured arrays. Such architecture provides high efficiency neutron detector devices by capturing substantially more carriers produced from high energy .alpha.-particles or .gamma.-photons generated by neutron interaction.

  2. Neutron in biology

    International Nuclear Information System (INIS)

    Niimura, Nobuo

    1997-01-01

    Neutron in biology can provide an experimental method of directly locating relationship of proteins and DNA. However, there are relatively few experimental study of such objects since it takes a lot of time to collect a sufficient number of Bragg reflections and inelastic spectra due to the low flux of neutron illuminating the sample. Since a next generation neutron source of JAERI will be 5MW spallation neutron source and its effective neutron flux will be 10 2 to 10 3 times higher than the one of JRR-3M, neutron in biology will open a completely new world for structural biology. (author)

  3. A neutron activation detector

    International Nuclear Information System (INIS)

    Ambardanishvili, T.S.; Kolomiitsev, M.A.; Zakharina, T.Y.; Dundua, V.J.; Chikhladze, N.V.

    1973-01-01

    The present invention concerns a neutron activation detector made from a moulded and hardened composition. According to the invention, that composition contains an activable substance constituted by at least two chemical elements and/or compounds of at least two chemical elements. Each of these chemical elements is capable of reacting with the neutrons forming radio-active isotopes with vatious levels of energy during desintegration. This neutron detector is mainly suitable for measuring integral thermal neutron and fast neutron fluxes during irradiation of the sample, and also for measuring the intensities of neutron fields [fr

  4. Very slow neutrons

    International Nuclear Information System (INIS)

    Frank, A.

    1983-01-01

    The history is briefly presented of the research so far of very slow neutrons and their basic properties are explained. The methods are described of obtaining very slow neutrons and the problems of their preservation are discussed. The existence of very slow neutrons makes it possible to perform experiments which may deepen the knowledge of the fundamental properties of neutrons. Their wavelength approximates that of visible radiation. The possibilities and use are discussed of neutron optical systems (neutron microscope) which could be an effective instrument for the study of the detailed arrangement, especially of organic substances. (B.S.)

  5. Reactor neutron dosimetry

    International Nuclear Information System (INIS)

    Najzer, M.; Pauko, M.; Glumac, B.; Acquah, I.N.; Moskon, F.

    1977-01-01

    An analysis of requirements and possibilities for experimental neutron spectrum determination during the reactor pressure vessel surveil lance programme is given. Fast neutron spectrum and neutron dose rate were measured in the Fast neutron irradiation facility of our TRIGA reactor. It was shown that the facility can be used for calibration of neutron dosimeters and for irradiation of samples sensitive to neutron radiation. The investigation of the unfolding algorithm ITER was continued. Based on this investigations are two specialized unfolding program packages ITERAD and ITERGS written this year. They are able to unfold data from activation detectors and NaI(T1) gamma spectrometer respectively

  6. Study of the elemental composition of Chenopodium Quinoa Willd by fast neutron activation analysis and X ray fluorescence analysis; Aplicacion del analisis por activacion neutronica y la fluorescencia de rayos X en el estudio de la composicion elemental de Chenopodium Quinoa Willd

    Energy Technology Data Exchange (ETDEWEB)

    Soto Moran, R L [Universidad de La Habana, La Habana (Cuba). Facultad de Fisica; Szegedi, S [Kossuth Lajos Tudomanyegyetem, Debrecen (Hungary). Fizikai Kemiai Intezete; Llopiz, J L [Universidad de La Habana, La Habana (Cuba). Instituto de Materiales y Reactivos para la Electronica

    1996-05-01

    By means of x-ray fluorescence and fast neutron activation analysis the nitrogen content has been determined in samples of roots, stems, leaf, flowers and grains from Quinua (Chenopodium Quinoa Willd), which was previously treated with fertilizer.

  7. Neutron stochastic transport theory with delayed neutrons

    International Nuclear Information System (INIS)

    Munoz-Cobo, J.L.; Verdu, G.

    1987-01-01

    From the stochastic transport theory with delayed neutrons, the Boltzmann transport equation with delayed neutrons for the average flux emerges in a natural way without recourse to any approximation. From this theory a general expression is obtained for the Feynman Y-function when delayed neutrons are included. The single mode approximation for the particular case of a subcritical assembly is developed, and it is shown that Y-function reduces to the familiar expression quoted in many books, when delayed neutrons are not considered, and spatial and source effects are not included. (author)

  8. 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

    modificar dentro de limites muy amplios los espectros de los neutrones causantes de la fision. En la memoria se describe el conjunto critico y sus diversas partes. Analizan los autores la eficacia comparada de la moderacion interna y externa, para reactores en que la razon de nucleos de moderador a nucleos de uranio, en el cuerpo, es muy pequena. Los experimentos demuestran que, arm. en el caso de los reflectores moderadores de gran espesor, esta baja razon ({partial_derivative}Be/{partial_derivative}{sup 235}U{approx_equal}1) conduce a un aumento de la masa critica. Gran parte de la memoria se dedica al analisis de los efectos heterogeneos en los reactores intermedios. Se demuestra que para un reactor en el que la razon {partial_derivative}Be/{partial_derivative}{sup 235}U este comprendida entre 30 y 40 distintos espesores (comprendidos entre 0,023 g/cm{sup 2} y 32 g/cm{sup 2}) de uranio muy enriquecido ejercen un efecto de magnitud constante sobre la reactividad del sistema. Se analizan las causas de la compensacion del efecto de apantallamient o del flujo neutronico por accion de capas de uranio de gran espesor. Los autores senalan un hecho interesante, a saber, el aumento de la eficacia del uranio en la proximidad de las barras de absorcion, que se observo experimentalment e en un conjunto en el que la razon {partial_derivative}Be/{partial_derivative}{sup 235}U era del orden de 200. Este hecho se explica por el acentuado descenso del nivel energetico de los neutrones absorbidos por el uranio. Para el mismo conjunto, presentan tambien datos sobre la eficacia de las barras de absorcion fabricadas con distintos materiales absorbentes. Exponen los resultados de las mediciones experimentales de la variacion de la densidad de los neutrones de distintas energias, en las cercanias de una barra de carburo de boro y la densidad de la captura neutroniea con m detector 1/v colocado en el interior de la barra. Por ultimo se exponen los metodos aplicados y los resultados obtenidos en

  9. The Problem of Storing Fission Products Arising from the Processing of Irradiated Uranium-Molybdenum Alloys; Probleme du Stockage des Produits de Fission en Provenance du Traitement des Alliages Uranium-Molybdene Irradies; 041f 0420 041e 0411 041b 0415 041c 0410 0425 0420 0410 041d 0415 041d 0418 042f 041e 0422 0425 041e 0414 041e 0412 041f 041e 0421 041b 0415 041f 0415 0420 0415 0420 0410 0411 041e 0422 041a 0418 041e 0411 041b 0423 0427 0415 041d 041d 041e 0413 041e 0421 041f 041b 0410 0412 0410 0423 0420 0410 041d - 041c 041e 041b 0418 0411 0414 0415 041d ; El Problema del Almacenamiento de los Productos de Fision Procedentes del Tratamiento de las Aleaciones Uranio-Molibdeno Irradiadas

    Energy Technology Data Exchange (ETDEWEB)

    Faugeras, P.; Kikindai, T. [Commissariat a l' Energie Atomique, Paris (France)

    1963-02-15

    el reactor, pero presentan serios inconvenientes en lo que respecta al almacenamiento de los productos de fision resultantes de su tratamiento. La insolubilidad del molibdeno impide concentrar por evaporacion las soluciones de los productos de fision. Por tal motivo, los autores han estudiado la posibilidad de solubilizar el molibdeno agregandole reactivos tales como el hierro o los iones fosforicos. De este modo, es posible obtener soluciones finales de 60 g/l Mo con hierro, 100 g/l Mo con PO{sub 4}H{sub 3}. Los volumenes que es preciso almacenar siguen siendo importantes (sobre todo con el hierro) y por eso se ha estudiado la calcinacion de los nitratos en un lecho fluidizado. La reaccion tiene lugar a los 400 Degree-Sign C aproximadamente. El comportamiento del rutenio y la friabilidad del solido calcinado (importante formacion de particulas menudas) ha inducido a los autores a reemplazar este procedimiento por el de preparacion de vidrios fosfAtados. (author) [Russian] Povedenie splavov uran-molibden v reaktore predstavljaet prakticheskij interes. Odnako voznikaet problema hranenija produktov delenija, kotorye poluchajutsja v rezul'tate ih pererabotki. V tom sluchae, kogda molibden nahoditsja v nerastvorennom sostojanii, ljuboe koncentrirovanie produktov delenija putem isparenija rastvora prakticheski nevozmozhno. Vot pochemu my orientirovalis' na izuchenie rastvorenija mo'libdena pribavleniem takih reagentov, kak zhelezo idi fosfat-iony. Mozhno poluchit' rastvor sostava: 60 g/l Mo s Re ili. 100 g/l Mo sPO{sub 4}H{sub 3} V jetom sluchae ob'edy, prednaznachennye dlja hranenija, uvelichivajutsja (osobenno pri dobavlenii Fe). Bylo izucheno prokalivanie nitratov v dvizhushhemsja sdoe. Reakcija prohodit pri temperature okolo 400 Degree-Sign C. Letuchest' rutenija i hrupkost' tverdogo prokalennogo veshhestva (vsledstvie obrazovanija znachitel'nogo kolichestva uglja) zastavila'nas otkazat'sja ot'jetogo processa i'perejti k izgotovleniju fosfatnyh stekol. (author)

  10. Neutron Beam Filters

    International Nuclear Information System (INIS)

    Adib, M.

    2011-01-01

    The purpose of filters is to transmit neutrons with selected energy, while remove unwanted ones from the incident neutron beam. This reduces the background, and the number of spurious. The types of commonly used now-a-day neutron filters and their properties are discussed in the present work. There are three major types of neutron filters. The first type is filter of selective thermal neutron. It transmits the main reflected neutrons from a crystal monochromate, while reject the higher order contaminations accompanying the main one. Beams coming from the moderator always contain unwanted radiation like fast neutrons and gamma-rays which contribute to experimental background and to the biological hazard potential. Such filter type is called filter of whole thermal neutron spectrum. The third filter type is it transmits neutrons with energies in the resonance energy range (En . 1 KeV). The main idea of such neutron filter technique is the use of large quantities of a certain material which have the deep interference minima in its total neutron cross-section. By transmitting reactor neutrons through bulk layer of such material, one can obtain the quasimonochromatic neutron lines instead of white reactor spectrum.

  11. Neutron anatomy

    Energy Technology Data Exchange (ETDEWEB)

    Bacon, G.E. [Univ. of Sheffield (United Kingdom)

    1994-12-31

    The familiar extremes of crystalline material are single-crystals and random powders. In between these two extremes are polycrystalline aggregates, not randomly arranged but possessing some preferred orientation and this is the form taken by constructional materials, be they steel girders or the bones of a human or animal skeleton. The details of the preferred orientation determine the ability of the material to withstand stress in any direction. In the case of bone the crucial factor is the orientation of the c-axes of the mineral content - the crystals of the hexagonal hydroxyapatite - and this can readily be determined by neutron diffraction. In particular it can be measured over the volume of a piece of bone, utilizing distances ranging from 1mm to 10mm. The major practical problem is to avoid the intense incoherent scattering from the hydrogen in the accompanying collagen; this can best be achieved by heat-treatment and it is demonstrated that this does not affect the underlying apatite. These studies of bone give leading anatomical information on the life and activities of humans and animals - including, for example, the life history of the human femur, the locomotion of sheep, the fracture of the legs of racehorses and the life-styles of Neolithic tribes. We conclude that the material is placed economically in the bone to withstand the expected stresses of life and the environment. The experimental results are presented in terms of the magnitude of the 0002 apatite reflection. It so happens that for a random powder the 0002, 1121 reflections, which are neighboring lines in the powder pattern, are approximately equal in intensity. The latter reflection, being of manifold multiplicity, is scarcely affected by preferred orientation so that the numerical value of the 0002/1121 ratio serves quite accurately as a quantitative measure of the degree of orientation of the c-axes in any chosen direction for a sample of bone.

  12. Neutron anatomy

    International Nuclear Information System (INIS)

    Bacon, G.E.

    1994-01-01

    The familiar extremes of crystalline material are single-crystals and random powders. In between these two extremes are polycrystalline aggregates, not randomly arranged but possessing some preferred orientation and this is the form taken by constructional materials, be they steel girders or the bones of a human or animal skeleton. The details of the preferred orientation determine the ability of the material to withstand stress in any direction. In the case of bone the crucial factor is the orientation of the c-axes of the mineral content - the crystals of the hexagonal hydroxyapatite - and this can readily be determined by neutron diffraction. In particular it can be measured over the volume of a piece of bone, utilizing distances ranging from 1mm to 10mm. The major practical problem is to avoid the intense incoherent scattering from the hydrogen in the accompanying collagen; this can best be achieved by heat-treatment and it is demonstrated that this does not affect the underlying apatite. These studies of bone give leading anatomical information on the life and activities of humans and animals - including, for example, the life history of the human femur, the locomotion of sheep, the fracture of the legs of racehorses and the life-styles of Neolithic tribes. We conclude that the material is placed economically in the bone to withstand the expected stresses of life and the environment. The experimental results are presented in terms of the magnitude of the 0002 apatite reflection. It so happens that for a random powder the 0002, 1121 reflections, which are neighboring lines in the powder pattern, are approximately equal in intensity. The latter reflection, being of manifold multiplicity, is scarcely affected by preferred orientation so that the numerical value of the 0002/1121 ratio serves quite accurately as a quantitative measure of the degree of orientation of the c-axes in any chosen direction for a sample of bone

  13. Basics of Neutrons for First Responders

    Energy Technology Data Exchange (ETDEWEB)

    Rees, Brian G. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2018-02-05

    These are slides from a presentation on the basics of neutrons. A few topics covered are: common origins of terrestrial neutron radiation, neutron sources, neutron energy, interactions, detecting neutrons, gammas from neutron interactions, neutron signatures in gamma-ray spectra, neutrons and NaI, neutron fluence to dose (msV), instruments' response to neutrons.

  14. Neutron radiography using neutron imaging plate

    International Nuclear Information System (INIS)

    Chankow, Nares; Wonglee, Sarinrat

    2008-01-01

    Full text: The aims of this research are to study properties of neutron imaging plate, to obtain a suitable condition for neutron radiography and to use the neutron imaging plate for testing of materials nondestructively. The experiments were carried out by using a neutron beam from the Thai Research Reactor TRR-1/M1 at a power of 1.2 MW. A BAS-ND 2040 FUJI neutron imaging plate and a MX125 Kodak X-ray film/Gadolinium neutron converter screen combination were tested for comparison. It was found that the photostimulated light (PSL) read out of the imaging plate was directly proportional to the exposure time. It was also found that radiography with neutron using the imaging plate was approximately 40 times faster than the conventional neutron radiography using x-ray film/Gd converter screen combination. The sensitivity of the imaging plate to gamma-rays was investigated by using gamma-rays from an 192 Ir and a 60 Co radiographic sources. The imaging plate was found to be 5-6 times less sensitive to gamma-rays than a FUJI BAS-MS 2040 gamma-ray imaging plate. Finally, some specimens were selected to be radiographed with neutrons using the imaging plate and the x-ray film/Gd converter screen combination in comparison to x-rays. Parts containing light elements could be clearly observed by the two neutron radiographic techniques. It could be concluded that the image quality from the neutron imaging plate was comparable to the conventional x-ray film/Gd converter screen combination but the exposure time could be approximately reduced by a factor of 40

  15. Apendicitis por Paracoccidioides brasiliensis.

    OpenAIRE

    MUÑOZ URRIBARRI, Ana Beatriz; CHAPARRO DAMMERT, Eduardo; FERRUFINO LLACH, Juan Carlos; VASQUEZ FLORES, Luciola

    2012-01-01

    La paracoccidioidomicosis es la micosis más prevalente en Sudamérica. La forma aguda afecta el sistema fagocítico mononuclear de niños y personas inmunocomprometidas. El compromiso gastrointestinal es frecuente y su patogenia implica diseminación hematógena y linfática. La linfadenomegalia abdominal causa obstrucción intestinal y abdomen agudo. En este artículo damos a conocer el caso de un niño con compromiso gastrointestinal por apendicitis. Este es el primer caso reportado de apendicitis p...

  16. Meningitis por Streptococcus suis

    OpenAIRE

    Geffner Sclarsky, D. E.; Moreno Muñoz, R.; Campillo Alpera, Mª.S.; Pardo Serrano, F.J.; Gómez Gómez, A.; Martínez-Lozano, Mª.D.

    2001-01-01

    La infección humana por Streptococcus suis (S. suis) es una zoonosis, con un riesgo ocupacional conocido y que suele presentarse como meningitis purulenta, que tiene baja mortalidad y frecuentes secuelas de hipoacusia y ataxia. Se han publicado menos de 150 casos humanos desde el informe original de hace 30 años. Hay una reconocida distribución geográfica viviendo la mayoría de los afectados en el norte de Europa y el sudeste Asiático. En España se han comunicado dos pacientes con enfermedad ...

  17. Por mil devaluados pesos

    Directory of Open Access Journals (Sweden)

    Annie Rodríguez Collázos

    2013-03-01

    Full Text Available El estudio de lo popular y lo urbano hasta ahora se ha centrado en el comportamiento y en algunas relaciones de los habitantes con su entorno. “Por mil devaluados pesos. Publicidad popular y urbana”, pretende explorar las formas de publicidad, dispersas en diferentes espacios populares y urbanos en Bogotá, identificando esquemas y formas características de sus propios códigos comunicativos; se centran en un objeto de estudio consistente en las estrategias publicitarias y los códigos comunicativos en los mensajes publicitarios populares en las subculturas de San Victorino, 7 de Agosto y Sanandresito de San José.

  18. Sources of polarized neutrons

    International Nuclear Information System (INIS)

    Walter, L.

    1983-01-01

    Various sources of polarized neutrons are reviewed. Monoenergetic source produced with unpolarized or polarized beams, white sources of polarized neutrons, production by transmissions through polarized hydrogen targets and polarized thermal neutronsare discussed, with appropriate applications included. (U.K.)

  19. Neutron delayed choice experiments

    International Nuclear Information System (INIS)

    Bernstein, H.J.

    1986-01-01

    Delayed choice experiments for neutrons can help extend the interpretation of quantum mechanical phenomena. They may also rule out alternative explanations which static interference experiments allow. A simple example of a feasible neutron test is presented and discussed. (orig.)

  20. Neutron radiation capture

    International Nuclear Information System (INIS)

    1986-01-01

    For all stable and experimentally studied radionuclides evaluated data are presented on cross sections of thermal neutrons, on resonance integrals and medium neutron cross sections with energy of 30 KeV. Refs, figs and tabs

  1. Neutron radiography in metallurgy

    International Nuclear Information System (INIS)

    Rant, J.; Ilic, R.

    1977-01-01

    The review surveys microneutronographic and neutron-induced autoradiographic techniques and their applications in metallurgy. A brief survey of applications of neutron radiography as a method of non-destructive testing to some macroscopic problems in metallurgy is included. (author)

  2. Applications of neutron irradiation

    International Nuclear Information System (INIS)

    Ito, Yasuo

    1999-01-01

    The present state of art of applications of neutron irradiation is overviewed taking neutron activation analysis, prompt gamma-ray analysis, fission/alpha track methods, boron neutron capture therapy as examples. What is common among them is that the technologies are nearly matured for wide use by non- nuclear scientists. But the environment around research reactors is not prospective. These applications should be encouraged by incorporating in the neutron science society. (author)

  3. Neutron beams for therapy

    International Nuclear Information System (INIS)

    Kuplenikov, Eh.L.; Dovbnya, A.N.; Telegin, Yu.N.; Tsymbal, V.A.; Kandybej, S.S.

    2011-01-01

    It was given the analysis and generalization of the study results carried out during some decades in many world countries on application of thermal, epithermal and fast neutrons for neutron, gamma-neutron and neutron-capture therapy. The main attention is focused on the practical application possibility of the accumulated experience for the base creation for medical research and the cancer patients effective treatment.

  4. Polarimetric neutron scattering

    International Nuclear Information System (INIS)

    Tasset, F.

    2001-01-01

    Polarimetric Neutron Scattering in introduced, both by, explaining methodological issues and the corresponding instrumental developments. After a short overview of neutron spin polarization and the neutron polarization 3d-vector a pictorial approach of the microscopic theory is used to show how a polarized beam interacts with lattice and magnetic Fourier components in a crystal. Examples are given of using Spherical Neutron Polarimetry (SNP) and the corresponding Cryopad polarimeter for the investigation of non-collinear magnetic structures. (R.P.)

  5. Reactor Neutron Sources

    International Nuclear Information System (INIS)

    Aksenov, V.L.

    1994-01-01

    The present status and the prospects for development of reactor neutron sources for neutron scattering research in the world are considered. The fields of application of neutron scattering relative to synchrotron radiation, the creation stages of reactors (steady state and pulsed) and their position in comparison with spallation neutron sources at present and in the foreseen future are discussed. (author). 15 refs.; 8 figs.; 3 tabs

  6. Properties of neutron sources

    International Nuclear Information System (INIS)

    1987-03-01

    The Conference presentations were divided into sessions devoted to the following topics: white neutron sources, primarily pulsed (6 papers); fast neutron fields (5 papers); Californium-252 prompt fission neutron spectra (14 papers); monoenergetic sources and filtered beams (11 papers); 14 MeV neutron sources (10 papers); selected special application (one paper); and a general interest session (4 papers). Individual abstracts were prepared separately for the papers

  7. Intense fusion neutron sources

    International Nuclear Information System (INIS)

    Kuteev, B. V.; Goncharov, P. R.; Sergeev, V. Yu.; Khripunov, V. I.

    2010-01-01

    The review describes physical principles underlying efficient production of free neutrons, up-to-date possibilities and prospects of creating fission and fusion neutron sources with intensities of 10 15 -10 21 neutrons/s, and schemes of production and application of neutrons in fusion-fission hybrid systems. The physical processes and parameters of high-temperature plasmas are considered at which optimal conditions for producing the largest number of fusion neutrons in systems with magnetic and inertial plasma confinement are achieved. The proposed plasma methods for neutron production are compared with other methods based on fusion reactions in nonplasma media, fission reactions, spallation, and muon catalysis. At present, intense neutron fluxes are mainly used in nanotechnology, biotechnology, material science, and military and fundamental research. In the near future (10-20 years), it will be possible to apply high-power neutron sources in fusion-fission hybrid systems for producing hydrogen, electric power, and technological heat, as well as for manufacturing synthetic nuclear fuel and closing the nuclear fuel cycle. Neutron sources with intensities approaching 10 20 neutrons/s may radically change the structure of power industry and considerably influence the fundamental and applied science and innovation technologies. Along with utilizing the energy produced in fusion reactions, the achievement of such high neutron intensities may stimulate wide application of subcritical fast nuclear reactors controlled by neutron sources. Superpower neutron sources will allow one to solve many problems of neutron diagnostics, monitor nano-and biological objects, and carry out radiation testing and modification of volumetric properties of materials at the industrial level. Such sources will considerably (up to 100 times) improve the accuracy of neutron physics experiments and will provide a better understanding of the structure of matter, including that of the neutron itself.

  8. Intense fusion neutron sources

    Science.gov (United States)

    Kuteev, B. V.; Goncharov, P. R.; Sergeev, V. Yu.; Khripunov, V. I.

    2010-04-01

    The review describes physical principles underlying efficient production of free neutrons, up-to-date possibilities and prospects of creating fission and fusion neutron sources with intensities of 1015-1021 neutrons/s, and schemes of production and application of neutrons in fusion-fission hybrid systems. The physical processes and parameters of high-temperature plasmas are considered at which optimal conditions for producing the largest number of fusion neutrons in systems with magnetic and inertial plasma confinement are achieved. The proposed plasma methods for neutron production are compared with other methods based on fusion reactions in nonplasma media, fission reactions, spallation, and muon catalysis. At present, intense neutron fluxes are mainly used in nanotechnology, biotechnology, material science, and military and fundamental research. In the near future (10-20 years), it will be possible to apply high-power neutron sources in fusion-fission hybrid systems for producing hydrogen, electric power, and technological heat, as well as for manufacturing synthetic nuclear fuel and closing the nuclear fuel cycle. Neutron sources with intensities approaching 1020 neutrons/s may radically change the structure of power industry and considerably influence the fundamental and applied science and innovation technologies. Along with utilizing the energy produced in fusion reactions, the achievement of such high neutron intensities may stimulate wide application of subcritical fast nuclear reactors controlled by neutron sources. Superpower neutron sources will allow one to solve many problems of neutron diagnostics, monitor nano-and biological objects, and carry out radiation testing and modification of volumetric properties of materials at the industrial level. Such sources will considerably (up to 100 times) improve the accuracy of neutron physics experiments and will provide a better understanding of the structure of matter, including that of the neutron itself.

  9. 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

  10. Isotopic neutron sources for neutron activation analysis

    International Nuclear Information System (INIS)

    Hoste, J.

    1988-06-01

    This User's Manual is an attempt to provide for teaching and training purposes, a series of well thought out demonstrative experiments in neutron activation analysis based on the utilization of an isotopic neutron source. In some cases, these ideas can be applied to solve practical analytical problems. 19 refs, figs and tabs

  11. Workshop on polarized neutron filters and polarized pulsed neutron experiments

    International Nuclear Information System (INIS)

    Itoh, Shinichi

    2004-07-01

    The workshop was held in KEK by thirty-three participants on April 26, 2004. The polarized neutron filter method was only discussed. It consists of three parts; the first part was discussed on the polarized neutron methods, the second part on the polarized neutron experiments and the third on the pulse neutron spectrometer and polarized neutron experiments. The six papers were presented such as the polarized 3 He neutron spin filter, neutron polarization by proton polarized filter, soft master and neutron scattering, polarized neutron in solid physics, polarization experiments by chopper spectroscope and neutron polarization system in superHRPD. (S.Y.)

  12. Spallation neutron sources

    International Nuclear Information System (INIS)

    Fraser, J.S.; Bartholomew, G.A.

    1983-01-01

    The principles and theory of spallation neutron sources are outlined and a comparison is given with other types of neutron source. A summary of the available accelerator types for spallation neutron sources and their advantages and disadvantages is presented. Suitable target materials are discussed for specific applications, and typical target assemblies shown. (U.K.)

  13. Shielded regenerative neutron detector

    International Nuclear Information System (INIS)

    Terhune, J.H.; Neissel, J.P.

    1978-01-01

    An ion chamber type neutron detector is disclosed which has a greatly extended lifespan. The detector includes a fission chamber containing a mixture of active and breeding material and a neutron shielding material. The breeding and shielding materials are selected to have similar or substantially matching neutron capture cross-sections so that their individual effects on increased detector life are mutually enhanced

  14. Prototype Neutron Energy Spectrometer

    International Nuclear Information System (INIS)

    Mitchell, Stephen; Mukhopadhyay, Sanjoy; Maurer, Richard; Wolff, Ronald

    2010-01-01

    The project goals are: (1) Use three to five pressurized helium tubes with varying polyethylene moderators to build a neutron energy spectrometer that is most sensitive to the incident neutron energy of interest. Neutron energies that are of particular interest are those from the fission neutrons (typically around 1-2 MeV); (2) Neutron Source Identification - Use the neutron energy 'selectivity' property as a tool to discriminate against other competing processes by which neutrons are generated (viz. Cosmic ray induced neutron production (ship effect), (a, n) reactions); (3) Determine the efficiency as a function of neutron energy (response function) of each of the detectors, and thereby obtain the composite neutron energy spectrum from the detector count rates; and (4) Far-field data characterization and effectively discerning shielded fission source. Summary of the presentation is: (1) A light weight simple form factor compact neutron energy spectrometer ready to be used in maritime missions has been built; (2) Under laboratory conditions, individual Single Neutron Source Identification is possible within 30 minutes. (3) Sources belonging to the same type of origin viz., (a, n), fission, cosmic cluster in the same place in the 2-D plot shown; and (4) Isotopes belonging to the same source origin like Cm-Be, Am-Be (a, n) or Pu-239, U-235 (fission) do have some overlap in the 2-D plot.

  15. Prototype Neutron Energy Spectrometer

    Energy Technology Data Exchange (ETDEWEB)

    Stephen Mitchell, Sanjoy Mukhopadhyay, Richard Maurer, Ronald Wolff

    2010-06-16

    The project goals are: (1) Use three to five pressurized helium tubes with varying polyethylene moderators to build a neutron energy spectrometer that is most sensitive to the incident neutron energy of interest. Neutron energies that are of particular interest are those from the fission neutrons (typically around 1-2 MeV); (2) Neutron Source Identification - Use the neutron energy 'selectivity' property as a tool to discriminate against other competing processes by which neutrons are generated (viz. Cosmic ray induced neutron production [ship effect], [a, n] reactions); (3) Determine the efficiency as a function of neutron energy (response function) of each of the detectors, and thereby obtain the composite neutron energy spectrum from the detector count rates; and (4) Far-field data characterization and effectively discerning shielded fission source. Summary of the presentation is: (1) A light weight simple form factor compact neutron energy spectrometer ready to be used in maritime missions has been built; (2) Under laboratory conditions, individual Single Neutron Source Identification is possible within 30 minutes. (3) Sources belonging to the same type of origin viz., (a, n), fission, cosmic cluster in the same place in the 2-D plot shown; and (4) Isotopes belonging to the same source origin like Cm-Be, Am-Be (a, n) or Pu-239, U-235 (fission) do have some overlap in the 2-D plot.

  16. Thermal neutron polarisation

    International Nuclear Information System (INIS)

    Satya Murthy, N.S.; Madhava Rao, L.

    1984-01-01

    The basic principle for the production of polarised thermal neutrons is discussed and the choice of various crystal monochromators surveyed. Brief mention of broad-spectrum polarisers is made. The application of polarised neutrons to the study of magnetisation density distributions in magnetic crystals, the dynamic concept of polarisation, principle and use of polarisation analysis, the neutron spin-echo technique are discussed. (author)

  17. Fundamental neutron physics

    International Nuclear Information System (INIS)

    Deslattes, R.; Dombeck, T.; Greene, G.; Ramsey, N.; Rauch, H.; Werner, S.

    1984-01-01

    Fundamental physics experiments of merit can be conducted at the proposed intense neutron sources. Areas of interest include: neutron particle properties, neutron wave properties, and fundamental physics utilizing reactor produced γ-rays. Such experiments require intense, full-time utilization of a beam station for periods ranging from several months to a year or more

  18. Neutron detection and radiography

    International Nuclear Information System (INIS)

    Bollen, R.H.; Van Esch, R.F.

    1975-01-01

    An improved method of recording neutron images is described which comprises imagewise irradiating with neutrons an intensifying screen containing a gadolinium compound that fluoresces when struck by x-rays and subjecting the fluorescent light pattern resulting from the impact of the neutrons on the screen onto a photographic material. (auth)

  19. Neutron Scattering Software

    Science.gov (United States)

    Home Page | Facilities | Reference | Software | Conferences | Announcements | Mailing Lists Neutron Scattering Banner Neutron Scattering Software A new portal for neutron scattering has just been established sets KUPLOT: data plotting and fitting software ILL/TAS: Matlab probrams for analyzing triple axis data

  20. International Neutron Radiography Newsletter

    DEFF Research Database (Denmark)

    Domanus, Joseph Czeslaw

    1986-01-01

    At the First World Conference on Neutron Radiography i t was decided to continue the "Neutron Radiography Newsletter", published previously by J.P. Barton, as the "International Neutron Radiography Newsletter" (INRNL), with J.C. Doraanus as editor. The British Journal of Non-Destructive Testing...

  1. Polarized Neutron Scattering

    OpenAIRE

    Roessli, B.; Böni, P.

    2000-01-01

    The technique of polarized neutron scattering is reviewed with emphasis on applications. Many examples of the usefulness of the method in various fields of physics are given like the determination of spin density maps, measurement of complex magnetic structures with spherical neutron polarimetry, inelastic neutron scattering and separation of coherent and incoherent scattering with help of the generalized XYZ method.

  2. 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

    rapport entre les quantites de graphite et de combustible. Une experience a l'aide d'un oscillateur a ondes carrees definit les valeurs de la reactivite centrale de quarante petits echantillons de differents materiaux, jusqu'a 10{sup -8} {Delta}k pour chaque ensemble. De plus, on fait osciller des sources artificielles de neutrons, etalonnees entre elles, pour determiner les differentes fonctions neutroniques importantes au centre du montage. On obtient les spectres en procedant a des mesures a l'aide de compteurs a fission comportant des feuilles etalonnees de seuils differents et d'un spectrometre a compteur au {sup 6}Li. Une methode de traitement numerique permettra de grouper toutes les mesures en un fichier autonome de sections efficaces moyennes par spectre. (author) [Spanish] La fase actual del programa del reactor epitermico de tipo avanzado, alimentado con torio, comprende una serie de experimentos integrales sobre fisica de los reactores, cuyo objeto es reunir datos sobre las secciones eficaces neutronicas en el intervalo 1 keV a 10 MeV. Se esta estudiando una serie de nueve conjuntos criticos de varias regiones, con acoplamiento termico-rapido, de forma pseudoesferica, del tipo alveolar de cuerpo dividido. Hasta ahora se han puesto en servicio tres conjuntos de esa indole. La region externa de conexion-desconexio n acciona una region de ensayo interna de forma esferica alimentada con {sup 233}U-Th, cuyo espectro neutronico se degrada progresivament e aumentando la razon grafito-combustible . Un experimento efectuado con un oscilador de onda cuadrada define los valores de la reactividad central de cuarenta pequenas muestras de diferentes materiales, hasta 10{sup -8} {Delta}k; para cada conjunto. Ademas, se hacen oscilar fuentes artificiales de neutrones intercalibradas para determinar las diferentes funciones neutronicas que revisten importancia en el centro del conjunto. Los espectros se obtienen procediendo a mediciones con contadores de fision

  3. Refractive neutron lens

    International Nuclear Information System (INIS)

    Petrov, P.V.; Kolchevsky, N.N.

    2013-01-01

    Model of the refractive neutron lens is proposed. System of N lenses acts as one thin lens with a complex refraction index n*. The maximum number N max of individual lenses for 'thick' neutron lens is calculated. Refractive neutron lens properties (resolution, focal depth) as function of resolution factor F 0 =ρbc/μ and depth of field factor dF 0 =λF 0 =λρbc/μ are calculated. It is shown that micro resolution of the refractive neutron optics is far from the wavelength in size and its open possibilities for progress in refractive neutron optics. (authors)

  4. Neutron scattering. Experiment manuals

    Energy Technology Data Exchange (ETDEWEB)

    Brueckel, Thomas; Heger, Gernot; Richter, Dieter; Roth, Georg; Zorn, Reiner (eds.)

    2010-07-01

    The following topics are dealt with: The thermal triple axis spectrometer PUMA, the high-resolution powder diffractometer SPODI, the hot single-crystal diffractometer HEiDi for structure analysis with neutrons, the backscattering spectrometer SPHERES, neutron polarization analysis with tht time-of-flight spectrometer DNS, the neutron spin-echo spectrometer J-NSE, small-angle neutron scattering with the KWS-1 and KWS-2 diffractometers, the very-small-angle neutron scattering diffractrometer with focusing mirror KWS-3, the resonance spin-echo spectrometer RESEDA, the reflectometer TREFF, the time-of-flight spectrometer TOFTOF. (HSI)

  5. Activation neutron detector

    International Nuclear Information System (INIS)

    Ambardanishvili, T.S.; Kolomiitsev, M.A.; Zakharina, T.Y.; Dundua, V.J.; Chikhladze, N.V.

    1976-01-01

    An activation neutron detector made as a moulded and cured composition of a material capable of being neutron-activated is described. The material is selected from a group consisting of at least two chemical elements, a compound of at least two chemical elements and their mixture, each of the chemical elements and their mixture, each of the chemical elements being capable of interacting with neutrons to form radioactive isotopes having different radiation energies when disintegrating. The material capable of being neutron-activated is distributed throughout the volume of a polycondensation resin inert with respect to neutrons and capable of curing. 17 Claims, No Drawings

  6. High energy neutron dosimeter

    International Nuclear Information System (INIS)

    Rai, K.S.F.

    1994-01-01

    A device for measuring dose equivalents in neutron radiation fields is described. The device includes nested symmetrical hemispheres (forming spheres) of different neutron moderating materials that allow the measurement of dose equivalents from 0.025 eV to past 1 GeV. The layers of moderating material surround a spherical neutron counter. The neutron counter is connected by an electrical cable to an electrical sensing means which interprets the signal from the neutron counter in the center of the moderating spheres. The spherical shape of the device allows for accurate measurement of dose equivalents regardless of its positioning. 2 figures

  7. Pulse neutron logging technique

    International Nuclear Information System (INIS)

    Bespalov, D.F.; Dylyuk, A.A.

    1975-01-01

    A new method of neutron-burst logging is proposed, residing in irradiating rocks with fast neutron bursts and registering the integrated flux burst of thermal and/or epithermal neutrons, from the moment of its initiation to that of full absorption. The obtaained value is representative of the rock properties (porosity, hydrogen content). The integrated flux in a burst of thermal and epithermal neutrons can be measured both by way of activation of a reference sample of a known chemical composition during the neutron burst and by recording the radiation of induced activity of the sample within an interval between two bursts. The proposed method features high informative value, accuracy and efficiency

  8. Neutron scattering. Experiment manuals

    International Nuclear Information System (INIS)

    Brueckel, Thomas; Heger, Gernot; Richter, Dieter; Roth, Georg; Zorn, Reiner

    2012-01-01

    The following topics are dealt with: The thermal triple-axis spectrometer PUMA, the high-resolution powder diffractometer SPODI, the hot single-crystal diffractometer HEiDi for structure analysis with neutrons, the backscattering spectrometer SPHERES, the neutron polarization analyzer DNS, the neutron spin-echo spectrometer J-NSE, the small-angle neutron diffractometers KWS-1/-2, the very-small-angle neutron diffractometer with focusing mirror KWS-3, the resonance spin-echo spectrometer RESEDA, the reflectometer TREFF, the time-of-flight spectrometer TOFTOF. (HSI)

  9. Neutron techniques in Safeguards

    International Nuclear Information System (INIS)

    Zucker, M.S.

    1982-01-01

    An essential part of Safeguards is the ability to quantitatively and nondestructively assay those materials with special neutron-interactive properties involved in nuclear industrial or military technology. Neutron techniques have furnished most of the important ways of assaying such materials, which is no surprise since the neutronic properties are what characterizes them. The techniques employed rely on a wide selection of the many methods of neutron generation, detection, and data analysis that have been developed for neutron physics and nuclear science in general

  10. Nanosecond neutron generator

    International Nuclear Information System (INIS)

    Lobov, S.I.; Pavlovskaya, N.G.; Pukhov, S.P.

    1991-01-01

    High-voltage nanosecond neutron generator for obtaining neutrons in D-T reaction is described. Yield of 6x10 6 neutron/pulse was generated in a sealed gas-filled diode with a target on the cathode by accelerating pulse voltage of approximately 0.5 MV and length at half-height of 0.5 ns and deuterium pressure of 6x10 -2 Torr. Ways of increasing neutron yield and possibilities of creating generators of nanosecond neutron pulses with great service life are considered

  11. Principles of neutron reflection

    International Nuclear Information System (INIS)

    Felcher, G.P.

    1988-08-01

    Neutron reflection is perhaps the most developed branch of slow neutrons optics, which in itself is a direct consequence of the undulatory nature of the neutron. After reviewing the basic types of interactions (nuclear and magnetic) between neutrons and matter, the formalism is introduced to calculate the reflectivity from a sample composed of stacked flat layers and, inversely, to calculate the stacking from reflectivity measurements. Finally, a brief survey of the applications of neutron reflection is given, both in technology and in fundamental research. 32 refs., 6 figs

  12. Grazing Incidence Neutron Optics

    Science.gov (United States)

    Gubarev, Mikhail V. (Inventor); Ramsey, Brian D. (Inventor); Engelhaupt, Darell E. (Inventor)

    2013-01-01

    Neutron optics based on the two-reflection geometries are capable of controlling beams of long wavelength neutrons with low angular divergence. The preferred mirror fabrication technique is a replication process with electroform nickel replication process being preferable. In the preliminary demonstration test an electroform nickel optics gave the neutron current density gain at the focal spot of the mirror at least 8 for neutron wavelengths in the range from 6 to 20.ANG.. The replication techniques can be also be used to fabricate neutron beam controlling guides.

  13. Neutron scattering. Experiment manuals

    International Nuclear Information System (INIS)

    Brueckel, Thomas; Heger, Gernot; Richter, Dieter; Roth, Georg; Zorn, Reiner

    2010-01-01

    The following topics are dealt with: The thermal triple axis spectrometer PUMA, the high-resolution powder diffractometer SPODI, the hot single-crystal diffractometer HEiDi for structure analysis with neutrons, the backscattering spectrometer SPHERES, neutron polarization analysis with tht time-of-flight spectrometer DNS, the neutron spin-echo spectrometer J-NSE, small-angle neutron scattering with the KWS-1 and KWS-2 diffractometers, the very-small-angle neutron scattering diffractrometer with focusing mirror KWS-3, the resonance spin-echo spectrometer RESEDA, the reflectometer TREFF, the time-of-flight spectrometer TOFTOF. (HSI)

  14. Sepsis por shigella flexneri

    Directory of Open Access Journals (Sweden)

    César Cabrera C

    2005-04-01

    Full Text Available Se presenta un caso raro de sepsis por Shigella flexneri en una paciente de 45 años de edad quien estando hospitalizada para el estudio de un tumor cerebral, requirió el uso de manitol y dosis altas de corticoides; luego de ello presenta deposiciones líquidas con moco y sangre, desarrolla síndrome de respuesta inflamatoria sistémica, luego se aísla Shigella flexneri en el hemocultivo; recibió tratamiento antibiótico con ciprofloxacina. Se describen las características del caso y se comenta de acuerdo con la revisión de literatura.

  15. Analysis of the microstructural evolution of the damage by neutron irradiation in the pressure vessel of a nuclear power reactor BWR; Analisis de la evolucion microestructural del dano por irradiacion neutronica en la vasija de presion de un reactor nuclear de potencia BWR

    Energy Technology Data Exchange (ETDEWEB)

    Moranchel y R, M.

    2012-07-01

    Nuclear reactor pressure vessel type BWR, installed in Mexico and in many other countries, are made of an alloy of low carbon steel. The American Society for Testing and Materials (Astm) classifies this alloy as A533-B, class 1. Both the vessel and other internal structures are continuously exposed to the neutron flux from the reactions of fission in nuclear fuel. A large number of neutrons reach the vessel and penetrate certain depth depending on their energy. Its penetration in the neutron collides with the nuclei of the atoms out of their positions in the crystal lattice of steel, producing vacancies, interstitial, segregations, among other defects, capable of affecting its mechanical properties. Analyze the micro-structural damage to the vessel due to neutron irradiation, is essential for reasons of integrity of this enclosure and safety of any nuclear power plant. The objective of this thesis work is theoretical and experimentally determine the microstructural damage of a type nuclear reactor vessel steel BWR, due to neutron radiation from the reactor core, using microscopic and spectroscopic techniques as well as Monte Carlo simulation. Microscopy Optical, Scanning Electron Microscopy, Transmission Electron Microscopy, Energy Dispersion of X-rays Spectrometry and X-rays Diffractometry were the techniques used in this research. These techniques helped in the characterization of both the basis of design of pressure vessel steel and steel irradiated, after eight years of neutron irradiation on the vessel, allowing know the surface morphology and crystal structures of the previous steel and post-irradiation, analyze the change in the microstructure of the steel vessel, morphological damage to surface level in an irradiated sample, among which are cavities in the order of microns produced by Atomic displacements due to the impact of neutronic, above all in the first layers of thickness of the vessel, the effect of swelling, regions of greater damage and Atomic

  16. Portable exhausters POR-004 SKID B, POR-005 SKID C, POR-006 SKID D storage plan

    International Nuclear Information System (INIS)

    Nelson, O.D.; Keller, G.M.

    1997-01-01

    This document provides a storage plan for portable exhausters POR-004 SKID B, POR-005 SKID C, AND POR-006 SKID D. The exhausters will be stored until they are needed by the TWRS (Tank Waste Remediation Systems) Saltwell Pumping Program. The storage plan provides criteria for portable exhauster storage, periodic inspections during storage, and retrieval from storage

  17. Experimental tests of the production process of Mo-99 fission in the hot cell; Pruebas experimentales del proceso de produccion de 99-Mo de fision en la celda caliente

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez M, V.; Lopez C, R

    1991-12-15

    The production method of {sup 99} Mo of fission obtains to this with a specific activity of several orders of great magnitude to the one obtained by other methods (as that of irradiation of a target constituted by an alloy or that of irradiation with neutrons of targets of molybdenum of natural isotopic composition or enriched with {sup 98} Mo) and perhaps the most important it is that by this method hundred of Ci of {sup 99} Mo can be obtained by production process. The development of the production process of {sup 99} Mo of fission, is closely linked with the development of techniques for the handling of high radioactivities, particularly the handling of radioactive gases, also with the deposit and elimination of radioactive wastes and with the construction of safety targets for its irradiation in a nuclear reactor. (Author)

  18. Analysis of the micro-structural damages by neutronic irradiation of the steel of reactor vessels of the nuclear power plant of Laguna Verde. Characterization of the design steel; Analisis de los danos micro-estructurales por irradiacion neutronica del acero de la vasija de los reactores de la Central Nuclear de Laguna Verde. Caracterizacion del acero de diseno

    Energy Technology Data Exchange (ETDEWEB)

    Moranchel y Rodriguez, M.; Garcia B, A. [IPN, Escuela Superior de Fisica y Matematicas, Departamento de Fisica, Av. Luis Enrique Erro s/n, Unidad Profesional Adolfo Lopez Mateos, Col. Lindavista, 07738 Mexico D. F. (Mexico); Longoria G, L. C., E-mail: mmoranchel@ipn.m [ININ, Direccion de Investigacion Cientifica, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2010-09-15

    The vessel of a nuclear reactor is one of the safety barriers more important in the design, construction and operation of the reactor. If the vessel results affected to the grade of to have fracture and/or cracks it is very probable the conclusion of their useful life in order to guarantee the nuclear safety and the radiological protection of the exposure occupational personnel, of the public and the environment avoiding the exposition to radioactive sources. The materials of the vessel of a nuclear reactor are exposed continually to the neutronic irradiation that generates the same nuclear reactor. The neutrons that impact to the vessel have the sufficient energy to penetrate certain depth in function of the energy of the incident neutron until reaching the repose or to be absorbed by some nucleus. In the course of their penetration, the neutrons interact with the nuclei, atoms, molecules and with the same crystalline nets of the vessel material producing vacuums, interstitial, precipitate and segregations among other defects that can modify the mechanical properties of the steel. The steel A533-B is the material with which is manufactured the vessel of the nuclear reactors of nuclear power plant of Laguna Verde, is an alloy that, among other components, it contains atoms of Ni that if they are segregated by the neutrons impact this would favor to the cracking of the same vessel. This work is part of an investigation to analyze the micro-structural damages of the reactor vessels of the nuclear power plant of Laguna Verde due to the neutronic irradiation which is exposed in a continuous way. We will show the characterization of the design steel of the vessel, what offers a comprehension about their chemical composition, the superficial topography and the crystalline nets of the steel A533-B. It will also allow analyze the existence of precipitates, segregates, the type of crystalline net and the distances inter-plains of the design steel of the vessel. (Author)

  19. Thermal neutron moderating device

    International Nuclear Information System (INIS)

    Takigami, Hiroyuki.

    1995-01-01

    In a thermal neutron moderating device, superconductive coils for generating magnetic fields capable of applying magnetic fields vertical to the longitudinal direction of a thermal neutron passing tube, and superconductive coils for magnetic field gradient for causing magnetic field gradient in the longitudinal direction of the thermal neutron passing tube are disposed being stacked at the outside of the thermal neutron passing tube. When magnetic field gradient is present vertically to the direction of a magnetic moment, thermal neutrons undergo forces in the direction of the magnetic field gradient in proportion to the magnetic moment. Then, the magnetic moment of the thermal neutrons is aligned with the direction vertical to the passing direction of the thermal neutrons, to cause the magnetic field gradient in the passing direction of the thermal neutrons. The speed of the thermal neutrons can be optionally selected and the wavelength can freely be changed by applying forces to the thermal neutrons and changing the extent and direction of the magnetic field gradient. Superconductive coils are used as the coils for generating magnetic fields and the magnetic field gradient in order to change extremely high energy of the thermal neutrons. (N.H.)

  20. Atlas of neutron resonances

    CERN Document Server

    Mughabghab, Said

    2018-01-01

    Atlas of Neutron Resonances: Resonance Properties and Thermal Cross Sections Z= 1-60, Sixth Edition, contains an extensive list of detailed individual neutron resonance parameters for Z=1-60, as well as thermal cross sections, capture resonance integrals, average resonance parameters and a short survey of the physics of thermal and resonance neutrons. The long introduction contains: nuclear physics formulas aimed at neutron physicists; topics of special interest such as valence neutron capture, nuclear level density parameters, and s-, p-, and d-wave neutron strength functions; and various comparisons of measured quantities with the predictions of nuclear models, such as the optical model. As in the last edition, additional features have been added to appeal to a wider spectrum of users. These include: spin-dependent scattering lengths that are of interest to solid-state physicists, nuclear physicists and neutron evaluators; calculated and measured Maxwellian average 5-keV and 30-keV capture cross sections o...

  1. Neutron image intensifier tubes

    International Nuclear Information System (INIS)

    Verat, M.; Rougeot, H.; Driard, B.

    1983-01-01

    The most frequently used techniques in neutron radiography employ a neutron converter consisting of either a scintillator or a thin metal sheet. The radiation created by the neutrons exposes a photographic film that is in contact with the converter: in the direct method, the film is exposed during the time that the object is irradiated with neutrons; in the transfer method, the film is exposed after the irradiation of the object with neutrons. In industrial non-destructive testing, when many identical objects have to be checked, these techniques have several disadvantages. Non-destructive testing systems without these disadvantages can be constructed around neutron-image intensifier tubes. A description and the operating characteristics of neutron-image intensifier tubes are given. (Auth.)

  2. Methods of neutron spectrometry

    International Nuclear Information System (INIS)

    Doerschel, B.

    1981-01-01

    The different methods of neutron spectrometry are based on the direct measurement of neutron velocity or on the use of suitable energy-dependent interaction processes. In the latter case the measuring effect of a detector is connected with the searched neutron spectrum by an integral equation. The solution needs suitable unfolding procedures. The most important methods of neutron spectrometry are the time-of-flight method, the crystal spectrometry, the neutron spectrometry by use of elastic collisions with hydrogen nuclei, and neutron spectrometry with the aid of nuclear reactions, especially of the neutron-induced activation. The advantages and disadvantages of these methods are contrasted considering the resolution, the measurable energy range, the sensitivity, and the experimental and computational efforts. (author)

  3. Neutrons as a probe

    International Nuclear Information System (INIS)

    Iizumi, Masashi

    1993-01-01

    As an introduction to the symposium a brief overview will be given about the features of neutrons as a probe. First it will be pointed out that the utilization of neutrons as a probe for investigating the structural and dynamical properties of condensed matters is a benign gift eventuated from the release of atomic energy initiated by Enrico Fermi exactly half century ago. Features of neutrons as a probe are discussed in accordance with the four basic physical properties of neutrons as an elementary particle; (1) no electric charge (the interaction with matter is nuclear), (2) the mass of neutron is 1 amu, (3) spin is 1/2 and (4) neutrons have magnetic dipole moment. Overview will be given on the uniqueness of neutrons as a probe and on the variety in the way they are used in the wide research area from the pure science to the industrial applications. (author)

  4. Neutron response study

    International Nuclear Information System (INIS)

    Endres, G.W.R.; Fix, J.J.; Thorson, M.R.; Nichols, L.L.

    1981-01-01

    Neutron response of the albedo type dosimeter is strongly dependent on the energy of the incident neutrons as well as the moderating material on the backside of the dosimeter. This study characterizes the response of the Hanford dosimeter for a variety of neutron energies for both a water and Rando phantom (a simulated human body consisting of an actual human skeleton with plastic for body muscles and certain organs). The Hanford dosimeter response to neutrons of different energies is typical of albedo type dosimeters. An approximate two orders of magnitude difference in response is observed between neutron energies of 100 keV and 10 MeV. Methods were described to compensate for the difference in dosimeter response between a laboratory neutron spectrum and the different spectra encountered at various facilities in the field. Generally, substantial field support is necessary for accurate neutron dosimetry

  5. Neutron structural biology

    Energy Technology Data Exchange (ETDEWEB)

    Niimura, Nobuo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-03-01

    Neutron diffraction provides an experimental method of directly locating hydrogen atoms in protein which play important roles in physiological functions. However, there are relatively few examples of neutron crystallography in biology since it takes a lot of time to collect a sufficient number of Bragg reflections due to the low flux of neutrons illuminating the sample. In order to overcome the flux problem, we have successfully developed the neutron IP, where the neutron converter, {sup 6}Li or Gd, was mixed with a photostimulated luminescence material on flexible plastic support. Neutron Laue diffraction 2A data from tetragonal lysozyme were collected for 10 days with neutron imaging plates, and 960 hydrogen atoms in the molecule and 157 bound water molecules were identified. These results explain the proposed hydrolysis mechanism of the sugar by the lysozyme molecule and that lysozyme is less active at pH7.0. (author)

  6. Control Multivariable por Desacoplo

    Directory of Open Access Journals (Sweden)

    Fernando Morilla

    2013-01-01

    Full Text Available Resumen: La interacción entre variables es una característica inherente de los procesos multivariables, que dificulta su operación y el diseño de sus sistemas de control. Bajo el paradigma de Control por desacoplo se agrupan un conjunto de metodologías, que tradicionalmente han estado orientadas a eliminar o reducir la interacción, y que recientemente algunos investigadores han reorientado con objetivos de solucionar un problema tan complejo como es el control multivariable. Parte del material descrito en este artículo es bien conocido en el campo del control de procesos, pero la mayor parte de él son resultados de varios años de investigación de los autores en los que han primado la generalización del problema, la búsqueda de soluciones de fácil implementación y la combinación de bloques elementales de control PID. Esta conjunción de intereses provoca que no siempre se pueda conseguir un desacoplo perfecto, pero que sí se pueda conseguir una considerable reducción de la interacción en el nivel básico de la pirámide de control, en beneficio de otros sistemas de control que ocupan niveles jerárquicos superiores. El artículo resume todos los aspectos básicos del Control por desacoplo y su aplicación a dos procesos representativos: una planta experimental de cuatro tanques acoplados y un modelo 4×4 de un sistema experimental de calefacción, ventilación y aire acondicionado. Abstract: The interaction between variables is inherent in multivariable processes and this fact may complicate their operation and control system design. Under the paradigm of decoupling control, several methodologies that traditionally have been addressed to cancel or reduce the interactions are gathered. Recently, this approach has been reoriented by several researchers with the aim to solve such a complex problem as the multivariable control. Parts of the material in this work are well known in the process control field; however, most of them are

  7. Neutron Research in HANARO

    International Nuclear Information System (INIS)

    Kim, Hark Rho

    2005-01-01

    HANARO (High-flux Advanced Neutron Application Reactor), which was designed and constructed by indigenous technology, is a world-class multi-purpose research reactor with a design thermal power of 30 MW, providing high neutron flux for various applications in Korea. HANARO has been operated since its first criticality in February 1995, and is now successfully utilized in such areas as neutron beam research, fuel and materials tests, radioisotopes and radiopharmaceuticals production, neutron activation analysis, and neutron transmutation doping, etc. A number of experimental facilities have been developed and installed since the beginning of reactor operation, and R and D activities for installing more facilities are actively under progress. Three flux traps in the core (CT, IR1, IR2), providing a high fast neutron flux, can be used for materials and fuel irradiation tests. They are also proper for production of high specific activity radioisotopes. Four vertical holes in the outer core region, abundant in epithermal neutrons, are used for fuel or material tests and radioisotope production. In the heavy water reflector region, 25 vertical holes with high quality thermal neutrons are located for radioisotope production, neutron activation analysis, neutron transmutation doping and cold neutron source installation. The two largest holes named NTD1 and NTD2 are for neutron transmutation doping, CNS for the cold neutron source installation, and LH for the irradiation of large targets. The high resolution powder diffractometer (HRPD) became operational in 1998, followed by the four circle diffractometer (FCD) in 1999, the residual stress instrument (RSI) in 2000, and the small angle neutron spectrometer (SANS) in 2001, respectively. HRPD and SANS became the most popular instruments these days, attracting wide range of users from academia, institutes and industries. We have made a lot of efforts during the last 10 years to develop some key components such as

  8. Neutron transportation simulator

    International Nuclear Information System (INIS)

    Uenohara, Yuzo.

    1995-01-01

    In the present invention, problems in an existent parallelized monte carlo method is solved, and behaviors of neutrons in a large scaled system are accurately simulated at a high speed. Namely, a neutron transportation simulator according to the monte carlo method simulates movement of each of neutrons by using a parallel computer. In this case, the system to be processed is divided based on a space region and an energy region to which neutrons belong. Simulation of neutrons in the divided regions is allotted to each of performing devices of the parallel computer. Tarry data and nuclear data of the neutrons in each of the regions are memorized dispersedly to memories of each of the performing devices. A transmission means for simulating the behaviors of the neutrons in the region by each of the performing devices, as well as transmitting the information of the neutrons, when the neutrons are moved to other region, to the performing device in a transported portion are disposed to each of the performing devices. With such procedures, simulation for the neutrons in the allotted region can be conducted with small capacity of memories. (I.S.)

  9. Instrumentation with polarized neutrons

    International Nuclear Information System (INIS)

    Boeni, P.; Muenzer, W.; Ostermann, A.

    2009-01-01

    Neutron scattering with polarization analysis is an indispensable tool for the investigation of novel materials exhibiting electronic, magnetic, and orbital degrees of freedom. In addition, polarized neutrons are necessary for neutron spin precession techniques that path the way to obtain extremely high resolution in space and time. Last but not least, polarized neutrons are being used for fundamental studies as well as very recently for neutron imaging. Many years ago, neutron beam lines were simply adapted for polarized beam applications by adding polarizing elements leading usually to unacceptable losses in neutron intensity. Recently, an increasing number of beam lines are designed such that an optimum use of polarized neutrons is facilitated. In addition, marked progress has been obtained in the technology of 3 He polarizers and the reflectivity of large-m supermirrors. Therefore, if properly designed, only factors of approximately 2-3 in neutron intensity are lost. It is shown that S-benders provide neutron beams with an almost wavelength independent polarization. Using twin cavities, polarized beams with a homogeneous phase space and P>0.99 can be produced without significantly sacrificing intensity. It is argued that elliptic guides, which are coated with large m polarizing supermirrors, provide the highest flux.

  10. Neutron wave optics studied with ultracold neutrons

    International Nuclear Information System (INIS)

    Steyerl, A.

    1984-01-01

    The author discusses experiments demonstrating or utilizing the wave properties of neutrons with wavelengths of about 100 nm. In particular the 'UCN gravity diffractometer' and the gravity spectrometer NESSIE (Neutronen-Schwerkraft-Spectrometrie) are illustrated. (Auth.)

  11. Neutron Optics: Towards Applications for Hot Neutrons

    International Nuclear Information System (INIS)

    Schanzer, C; Schneider, M; Böni, P

    2016-01-01

    Supermirrors with large critical angles of reflection, i.e. large index m are an essential ingredient to transport, focus and polarise neutrons over a wide range of energy. Here we summarise the recent developments of supermirror with very large critical angles of reflection and high reflectivity that were conducted at SwissNeutronics as well as their implementation in devices. Approaching critical angles m = 8 times the critical angle of natural nickel makes new applications possible and extends the use of reflection optics towards the regime of hot and epithermal neutrons. Based on comparisons of simulations with experiment we demonstrate future possibilities of applications of large-m supermirrors towards devices for neutrons with short wavelength. (paper)

  12. A polarizing neutron periscope for neutron imaging

    International Nuclear Information System (INIS)

    Schulz, Michael; Boeni, Peter; Calzada, Elbio; Muehlbauer, Martin; Neubauer, Andreas; Schillinger, Burkhard

    2009-01-01

    Optical neutron polarizers like guides or benders destroy the collimation of a neutron beam due to multiple reflections or scattering. This makes them unsuitable for their use in polarized neutron radiography, because the beam collimation is essential to obtain high spatial resolution. We have developed a neutron polarizer based on the principle of an optical periscope with a zigzag double reflection on two parallel high-m supermirror polarizers. If the supermirrors are perfectly parallel and flat, the beam collimation is left unchanged by such a device. A first proof of concept version of this type of polarizer was built and tested. We expect to achieve a beam polarization of up to 99% with an improved version yet to be built.

  13. Pulsed neutron porosity logging system

    International Nuclear Information System (INIS)

    Smith, H.D. Jr.; Smith, M.P.; Schultz, W.E.

    1978-01-01

    An improved pulsed neutron porosity logging system is provided in the present invention. A logging tool provided with a 14 MeV pulsed neutron source, an epithermal neutron detector, and a fast neutron detector is moved through a borehole. Repetitive bursts of neutrons irradiate the earth formations and, during the bursts, the fast neutron population is sampled. During the interval between bursts the epithermal neutron population is sampled along with background gamma radiation due to lingering thermal neutrons. The fast and epithermal neutron population measurements are combined to provide a measurement of formation porosity

  14. Bouncing neutrons and the neutron centrifuge

    International Nuclear Information System (INIS)

    Watson, P J S

    2003-01-01

    The recent observation of the quantum state of the neutron bouncing freely under gravity allows some novel experiments. A possible method of purifying the ground state is given. We investigate two possible applications. It appears that the state could not be used to set better limits on the electric dipole moment of the neutron. However, it would be possible to use the state to set limits on modifications of gravity at short distances

  15. Status of spallation neutron source

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-03-01

    Existing and planned facilities using proton accelerator driven spallation neutron source are reviewed. These include new project of neutron science proposed from Japan Atomic Energy Research Institute. The present status of facility requirement and accelerator technology leads us to new era of neutron science such as neutron scattering research and nuclear transmutation study using very intense neutron source. (author)

  16. Pulsed and Static Neutron Measurements in Light-Water and Heavy-Water Exponentials; Mesures par les Methodes Pulsee et Statique dans les Ensembles Exponentiels a Eau Legere et a Eau Lourde; Izmerenie impul'snykh i staticheskikh nejtronov v ehksponentsial'nykh ustanovkakh s obychnoj i tyazheloj vodoj; Mediciones por los Metodos Pulsados y Estaticos en Conjuntos Exponenciales de Agua Ligera y Agua Pesada

    Energy Technology Data Exchange (ETDEWEB)

    Parkinson, T. F.; Perez, R. B.; Fry, D. N.; Hartley, R. H.; Smith, S. P.D.; Diaz, N. J. [University of Florida, Gainesville, FL (United States)

    1964-04-15

    deduce mediante una formula sencilla en la que intervienen {lambda}{sub 0}, k{sub {infinity}} {tau}, L{sup 2} y B{sup 2} en la cual B{sup 2} satisface la ecuacion critica de dos zonas. La probabilidad de ausencia de escape de los neutrones rapidos se expreso por la teoria de la edad de Fermi. El metodo de calculo consistio en asignar un valor aproximado a la constante de desintegracion {lambda}, y en operar luego por iteracion hasta encontrar un valor de B{sup 2} compatible con la ecuacion critica y las condiciones limite. Tambien se ensayaron dos otroe modelos, a saber: Modelo B: Se imagina un sistema de dos zonas y un solo grupo en el que el factor B{sup 2}{sub g} del nucleo de Fermi se toma como laplaciano geometrico del sistema desnudo equivalente, teniendo en cuenta la economia del reflector. Modelo C: Se imagina un sistema desnudo de dos grupos en el que se tiene en cuenta la economia del reflector. Al comparar las constantes de desintegracion calculadas y obtenidas experimentalmente, se comprueba que solo asegura una concordancia satisfactoria el modelo A. Esto permite llegar a las siguientes conclusiones: 1. La presencia del reflector ejerce una influencia considerable sobre la fisica del sistema pulsado. La hipotesis segun la cual se admite una economia debida al reflector no es valida en todos los casos. 2. El valor de la constante de decrecimiento {lambda} depende en gran medida del valor atribuido a la probabilidad de ausencia de escape de los neutrones rapidos. Los experimentos indican que la tecnica de los neutrones pulsados permite determinar k{sub {infinity}} en conjuntos heterogeneos de pequeflas dimensiones. Los autores estan llevando a cabo trabajos con barras huecas de uranio que permiten simular el empleo de refrigerantes organicos. (author) [Russian] Dolgoe vremja dlja opredelenija material'nogo laplasiana razmnozhajushhej sredy ispol'zovalsja jeksponencial'nyj jeksperiment. Sovsem nedavno dlja izmerenija sobstvennogo znachenija vremeni {lambda}, iz

  17. Prototype Stilbene Neutron Collar

    Energy Technology Data Exchange (ETDEWEB)

    Prasad, M. K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Shumaker, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Snyderman, N. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Verbeke, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wong, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-10-26

    A neutron collar using stilbene organic scintillator cells for fast neutron counting is described for the assay of fresh low enriched uranium (LEU) fuel assemblies. The prototype stilbene collar has a form factor similar to standard He-3 based collars and uses an AmLi interrogation neutron source. This report describes the simulation of list mode neutron correlation data on various fuel assemblies including some with neutron absorbers (burnable Gd poisons). Calibration curves (doubles vs 235U linear mass density) are presented for both thermal and fast (with Cd lining) modes of operation. It is shown that the stilbene collar meets or exceeds the current capabilities of He-3 based neutron collars. A self-consistent assay methodology, uniquely suited to the stilbene collar, using triples is described which complements traditional assay based on doubles calibration curves.

  18. Biological effects of neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Ogiu, Toshiaki; Ohmachi, Yasushi; Ishida, Yuka [National Inst. of Radiological Sciences, Chiba (JP)] [and others

    2003-03-01

    Although the occasion to be exposed to neutrons is rare in our life, except for nuclear accidents like in the critical accident at Tokai-mura in 1999, countermeasures against accident should be always prepared. In the Tokai-mura accident, residents received less than 21 mSv of neutrons and gamma rays. The cancer risks and fetal effects of low doses of neutrons were matters of concern among residents. The purpose of this program is to investigate the relative biological effectiveness (RBE) for leukemias, and thereby to assess risks of neutrons. Animal experiments are planed to obtain the following RBEs: (1) RBE for the induction of leukemias in mice and (2) RBE for effects on fetuses. Cyclotron fast neutrons (10 MeV) and electrostatic accelerator-derived neutrons (2 MeV) are used for exposure in this program. Furthermore, cytological and cytogenetic analyses will be performed. (author)

  19. Neutron sources and applications

    Energy Technology Data Exchange (ETDEWEB)

    Price, D.L. [ed.] [Argonne National Lab., IL (United States); Rush, J.J. [ed.] [National Inst. of Standards and Technology, Gaithersburg, MD (United States)

    1994-01-01

    Review of Neutron Sources and Applications was held at Oak Brook, Illinois, during September 8--10, 1992. This review involved some 70 national and international experts in different areas of neutron research, sources, and applications. Separate working groups were asked to (1) review the current status of advanced research reactors and spallation sources; and (2) provide an update on scientific, technological, and medical applications, including neutron scattering research in a number of disciplines, isotope production, materials irradiation, and other important uses of neutron sources such as materials analysis and fundamental neutron physics. This report summarizes the findings and conclusions of the different working groups involved in the review, and contains some of the best current expertise on neutron sources and applications.

  20. Neutron sources and applications

    International Nuclear Information System (INIS)

    Price, D.L.; Rush, J.J.

    1994-01-01

    Review of Neutron Sources and Applications was held at Oak Brook, Illinois, during September 8--10, 1992. This review involved some 70 national and international experts in different areas of neutron research, sources, and applications. Separate working groups were asked to (1) review the current status of advanced research reactors and spallation sources; and (2) provide an update on scientific, technological, and medical applications, including neutron scattering research in a number of disciplines, isotope production, materials irradiation, and other important uses of neutron sources such as materials analysis and fundamental neutron physics. This report summarizes the findings and conclusions of the different working groups involved in the review, and contains some of the best current expertise on neutron sources and applications

  1. Neutron scattering and magnetism

    International Nuclear Information System (INIS)

    Mackintosh, A.R.

    1983-01-01

    Those properties of the neutron which make it a unique tool for the study of magnetism are described. The scattering of neutrons by magnetic solids is briefly reviewed, with emphasis on the information on the magnetic structure and dynamics which is inherent in the scattering cross-section. The contribution of neutron scattering to our understanding of magnetic ordering, excitations and phase transitions is illustrated by experimental results on a variety of magnetic crystals. (author)

  2. The Advanced Neutron Source

    International Nuclear Information System (INIS)

    Hayter, J.B.

    1989-01-01

    The Advanced Neutron Source (ANS) is a new user experimental facility planned to be operational at Oak Ridge in the late 1990's. The centerpiece of the ANS will be a steady-state research reactor of unprecedented thermal neutron flux (φ th ∼ 9·10 19 m -2 ·s -1 ) accompanied by extensive and comprehensive equipment and facilities for neutron-based research. 5 refs., 5 figs

  3. Neutrons and Nuclear Engineering

    International Nuclear Information System (INIS)

    Ekkebus, Allen E.

    2007-01-01

    Oak Ridge National Laboratory hosted two workshops in April 2007 relevant to nuclear engineering education. In the Neutron Stress, Texture, and Phase Transformation for Industry workshop (http://neutrons.ornl.gov/workshops/nst2/), several invited speakers gave examples of neutron stress mapping for nuclear engineering applications. These included John Root of National Research Council of Canada, Mike Fitzpatrick of the UK's Open University, and Yan Gao of GE Global Research on their experiences with industrial and academic uses of neutron diffraction. Xun-Li Wang and Camden Hubbard described the new instruments at ORNL that can be used for such studies. This was preceded by the Neutrons for Materials Science and Engineering educational symposium (http://neutrons.ornl.gov/workshops/edsym2007). It was directed to the broad materials science and engineering community based in universities, industry and laboratories who wish to learn what the neutron sources in the US can provide for enhancing the understanding of materials behavior, processing and joining. Of particular interest was the presentation of Donald Brown of Los Alamos about using 'Neutron diffraction measurements of strain and texture to study mechanical behavior of structural materials.' At both workshops, the ORNL neutron scattering instruments relevant to nuclear engineering studies were described. The Neutron Residual Stress Mapping Facility (NRSF2) is currently in operation at the High Flux Isotope Reactor; the VULCAN Engineering Materials Diffractometer will begin commissioning in 2008 at the Spallation Neutron Source. For characteristics of these instruments, as well as details of other workshops, meetings, capabilities, and research proposal submissions, please visit http://neutrons.ornl.gov. To submit user proposals for time on NRSF2 contact Hubbard at hubbardcratornl.gov

  4. The neutron porosity tool

    International Nuclear Information System (INIS)

    Oelgaard, P.L.

    1988-01-01

    The report contains a review of available information on neutron porosity tools with the emphasis on dual thermal-neutron-detector porosity tools and epithermal-neutron-detector porosity tools. The general principle of such tools is discussed and theoretical models are very briefly reviewed. Available data on tool designs are summarized with special regard to the source-detector distance. Tool operational data, porosity determination and correction of measurements are briefly discussed. (author) 15 refs

  5. Individual neutron dosimetry

    International Nuclear Information System (INIS)

    Mauricio, C.L.P.

    1987-01-01

    The most important concepts and development in individual neutron dosimetry are presented, especially the dosimetric properties of the albedo technique. The main problem in albedo dosimetry is to calibrate the dosemeter in the environs of each neutron source. Some of the most used calibration techniques are discussed. The IRD albedo dosemeter used in the routine neutron individual monitoring is described in detail. Its dosimetric properties and calibration methods are discussed. (Author) [pt

  6. The advanced neutron source

    International Nuclear Information System (INIS)

    Raman, S.; Hayter, J.B.

    1990-01-01

    The Advanced Neutron Source (ANS) is a new user experimental facility planned to be operational at Oak Ridge in the late 1990's. The centerpiece of the ANS will be a steady-state research reactor of unprecedented thermal neutron flux (φ th ∼ 8 x 10 19 m -2 ·s -1 ) accompanied by extensive and comprehensive equipment and facilities for neutron-based research

  7. ATR neutron spectral characterization

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, J.W.; Anderl, R.A.

    1995-11-01

    The Advanced Test Reactor (ATR) at INEL provides intense neutron fields for irradiation-effects testing of reactor material samples, for production of radionuclides used in industrial and medical applications, and for scientific research. Characterization of the neutron environments in the irradiation locations of the ATR has been done by means of neutronics calculations and by means of neutron dosimetry based on the use of neutron activation monitors that are placed in the various irradiation locations. The primary purpose of this report is to present the results of an extensive characterization of several ATR irradiation locations based on neutron dosimetry measurements and on least-squares-adjustment analyses that utilize both neutron dosimetry measurements and neutronics calculations. This report builds upon the previous publications, especially the reference 4 paper. Section 2 provides a brief description of the ATR and it tabulates neutron spectral information for typical irradiation locations, as derived from the more historical neutron dosimetry measurements. Relevant details that pertain to the multigroup neutron spectral characterization are covered in section 3. This discussion includes a presentation on the dosimeter irradiation and analyses and a development of the least-squares adjustment methodology, along with a summary of the results of these analyses. Spectrum-averaged cross sections for neutron monitoring and for displacement-damage prediction in Fe, Cr, and Ni are given in section 4. In addition, section4 includes estimates of damage generation rates for these materials in selected ATR irradiation locations. In section 5, the authors present a brief discussion of the most significant conclusions of this work and comment on its relevance to the present ATR core configuration. Finally, detailed numerical and graphical results for the spectrum-characterization analyses in each irradiation location are provided in the Appendix.

  8. Neutrons for probing matter

    International Nuclear Information System (INIS)

    Torres, F. Ed.; Mazzucchetti, D.

    2008-01-01

    The authors tell the story of the French Orphee reactor located in Saclay from the decision to build it in the seventies, to its commissioning in 1980, to its upgrading in the nineties and to its today's operating life. As early as its feasibility studies Orphee has been designed as a dual-purpose reactor: scientific research for instance in crystallography and magnetism, and industrial uses like neutron radiography, silicon doping or radionuclide production. This book is divided into 4 parts: 1) the neutron: an explorer of the matter, 2) the Orphee reactor: a neutron source, 3) the adventurers of the matter: Leon Brillouin laboratory's staff, and 4) the perspectives for neutrons

  9. Spallation neutrons pulsed sources

    International Nuclear Information System (INIS)

    Carpenter, J.

    1996-01-01

    This article describes the range of scientific applications which can use these pulsed neutrons sources: Studies on super fluids, measures to verify the crawling model for the polymers diffusion; these sources are also useful to study the neutron disintegration, the ultra cold neutrons. In certain applications which were not accessible by neutrons diffusion, for example, radiations damages, radionuclides production and activation analysis, the spallation sources find their use and their improvement will bring new possibilities. Among others contributions, one must notice the place at disposal of pulsed muons sources and neutrinos sources. (N.C.). 3 figs

  10. Microcomputerized neutron moisture gauge

    International Nuclear Information System (INIS)

    Liu Shengkang; Mei Yu

    1987-01-01

    A microcomputerized neutron moisture gauge is introduced. This gauge consists of a neutron moisture sensor and instruments. It is developed from the neutron moisture gauge for concrete mixer. A TECH-81 single card microcomputer is used for count, computation and display. It has the function of computing compensated quantity of sand. It can acquire the data from several neutron sensors by the multichanneling sampling, therefore it can measure moisture values of sand in several hoppers simultaneously. The precision of the static state calibration curve is 0.24% wt. The error limits of the dynamic state check is < 0.50% wt

  11. Neutrons from Antiproton Irradiation

    DEFF Research Database (Denmark)

    Bassler, Niels; Holzscheiter, Michael; Petersen, Jørgen B.B.

    the neutron spectrum. Additionally, we used a cylindrical polystyrene loaded with several pairs of thermoluminescent detectors containing Lithium-6 and Lithium-7, which effectively detects thermalized neutrons. The obtained results are compared with FLUKA imulations. Results: The results obtained...... spectrum is very low, and does not pose a problem for radiation therapy. However, the contribution from fast neutrons is much more significant. The dose equivalent contribution from neutrons originate from the patient alone and reaches levels which are found in passive moderated proton therapy. The exact...

  12. Introduction to neutron stars

    Energy Technology Data Exchange (ETDEWEB)

    Lattimer, James M. [Dept. of Physics and Astronomy, Stony Brook University, Stony Brook, NY 11794-3800 (United States)

    2015-02-24

    Neutron stars contain the densest form of matter in the present universe. General relativity and causality set important constraints to their compactness. In addition, analytic GR solutions are useful in understanding the relationships that exist among the maximum mass, radii, moments of inertia, and tidal Love numbers of neutron stars, all of which are accessible to observation. Some of these relations are independent of the underlying dense matter equation of state, while others are very sensitive to the equation of state. Recent observations of neutron stars from pulsar timing, quiescent X-ray emission from binaries, and Type I X-ray bursts can set important constraints on the structure of neutron stars and the underlying equation of state. In addition, measurements of thermal radiation from neutron stars has uncovered the possible existence of neutron and proton superfluidity/superconductivity in the core of a neutron star, as well as offering powerful evidence that typical neutron stars have significant crusts. These observations impose constraints on the existence of strange quark matter stars, and limit the possibility that abundant deconfined quark matter or hyperons exist in the cores of neutron stars.

  13. Neutron detection technique

    International Nuclear Information System (INIS)

    Oblath, N.S.; Poon, A.W.P.

    2000-01-01

    The Sudbury Neutrino Observatory (SNO) has the ability to measure the total flux of all active flavors of neutrinos using the neutral current reaction, whose signature is a neutron. By comparing the rates of the neutral current reaction to the charged current reaction, which only detects electron neutrinos, one can test the neutrino oscillation hypothesis independent of solar models. It is necessary to understand the neutron detection efficiency of the detector to make use of the neutral current reaction. This report demonstrates a coincidence technique to identify neutrons emitted from the 252 Cf neutron calibration source. The source releases on average four neutrons when a 252 Cf nucleus spontaneously fissions. Each neutron is detected as a separate event when the neutron is captured by a deuteron, releasing a gamma ray of approximately 6.25 MeV. This gamma ray is in turn detected by the photomultiplier tube (PMT) array. By investigating the time and spatial separation between neutron-like events, it is possible to obtain a pure sample of neutrons for calibration study. Preliminary results of the technique applied to two calibration runs are presented

  14. Neutron scattering. Experiment manuals

    International Nuclear Information System (INIS)

    Brueckel, Thomas; Heger, Gernot; Richter, Dieter; Roth, Georg; Zorn, Reiner

    2014-01-01

    The following topics are dealt with: The thermal triple-axis spectrometer PUMA, the high-resolution powder diffractometer SPODI, the hot-single-crystal diffractometer HEiDi, the three-axis spectrometer PANDA, the backscattering spectrometer SPHERES, the DNS neutron-polarization analysis, the neutron spin-echo spectrometer J-NSE, small-angle neutron scattering at KWS-1 and KWS-2, a very-small-angle neutron scattering diffractometer with focusing mirror, the reflectometer TREFF, the time-of-flight spectrometer TOFTOF. (HSI)

  15. Neutrons in biology

    International Nuclear Information System (INIS)

    Funahashi, Satoru; Niimura, Nobuo.

    1993-01-01

    The start of JRR-3M in 1990 was a great epoch to the neutron scattering research in Japan. Abundant neutron beam generated by the JRR-3M made it possible to widen the research field of neutron scattering in Japan. In the early days of neutron scattering, biological materials were too difficult object to be studied by neutrons not only because of their complexity but also because of the strong incoherent scattering by hydrogen. However, the remarkable development of the recent neutron scattering and its related sciences, as well as the availability of higher flux, has made the biological materials one of the most attractive subjects to be studied by neutrons. In early September 1992, an intensive workshop titled 'Neutrons in Biology' was held in Hitachi City by making use of the opportunity of the 4th International Conference on Biophysics and Synchrotron Radiation (BSR92) held in Tsukuba. The workshop was organized by volunteers who are eager to develop the researches in this field in Japan. Numbers of outstanding neutron scattering biologists from U.S., Europe and Asian countries met together and enthusiastic discussions were held all day long. The editors believe that the presentations at the workshop were so invaluable that it is absolutely adequate to put them on record as an issue of JAERI-M and to make them available for scientists to refer to in order to further promote the research in the future. (author)

  16. Polycapillary neutron lenses

    International Nuclear Information System (INIS)

    Mildner, D.F.R.

    1997-01-01

    The principle of multiple mirror reflection from smooth surfaces at small grazing angles enables the transport and guiding of high intensity slow neutron beams to locations of low background for neutron scattering and absorption experiments and to provide facilities for multiple instruments. Curved guides have been widely used at cold neutron facilities to remove the unwanted radiation (fast neutrons and gamma rays) from the beam without the use of filters. A typical guide has transverse dimensions of 50 mm and, with a radius of curvature of 1 km, transmits wavelengths longer than 5 A. Much tighter curves requires narrower transverse dimensions, otherwise there is little transmission. Typical neutron benders have a number of slots with transverse dimensions of ∼5 mm. Based on the same principle but using a different technology, recent developments in glass polycapillary fibers have produced miniature versions of neutron guides. Fibers with many thousands of channels having sizes of ∼ 10 μm enable beams of long wavelength neutrons (λ > 4 A) to be transmitted efficiently in a radius of curvature as small as a fraction of 1 m. A large collection of these miniature versions of neutron guides can be used to bend the neutron trajectories such that the incident beam can be focused. (author)

  17. Neutron structural biology

    International Nuclear Information System (INIS)

    Niimura, Nobuo

    1999-01-01

    Neutron structural biology will be one of the most important fields in the life sciences which will interest human beings in the 21st century because neutrons can provide not only the position of hydrogen atoms in biological macromolecules but also the dynamic molecular motion of hydrogen atoms and water molecules. However, there are only a few examples experimentally determined at present because of the lack of neutron source intensity. Next generation neutron source scheduled in JAERI (Performance of which is 100 times better than that of JRR-3M) opens the life science of the 21st century. (author)

  18. JRR-3 neutron radiography facility

    International Nuclear Information System (INIS)

    Matsubayashi, M.; Tsuruno, A.

    1992-01-01

    JRR-3 neutron radiography facility consists of thermal neutron radiography facility (TNRF) and cold neutron radiography facility (CNRF). TNRF is installed in JRR-3 reactor building. CNRF is installed in the experimental beam hall adjacent to the reactor building. (author)

  19. Thermoluminescence albedo-neutron dosimetry

    International Nuclear Information System (INIS)

    Strand, T.; Storruste, A.

    1986-10-01

    The report discusses neutron detection with respect to dosimetry and compares different thermoluminescent dosimetry materials for neutron dosimetry. Construction and calibration of a thermoluminescence albedo neutron dosemeter, developed by the authors, is described

  20. Determination of the archaeological origin of ceramic fragments characterized by neutron activation analysis, by means of the application of multivariable statistical analysis techniques;Determinacion del origen de fragmentos de ceramica arqueologica caracterizados con analisis por activacion neutronica, mediante la aplicacion de tecnicas de analisis estadistico multivariable

    Energy Technology Data Exchange (ETDEWEB)

    Almazan T, M. G.; Jimenez R, M.; Monroy G, F.; Tenorio, D. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Rodriguez G, N. L. [Instituto Mexiquense de Cultura, Subdireccion de Restauracion y Conservacion, Hidalgo poniente No. 1013, 50080 Toluca, Estado de Mexico (Mexico)

    2009-07-01

    The elementary composition of archaeological ceramic fragments obtained during the explorations in San Miguel Ixtapan, Mexico State, was determined by the neutron activation analysis technique. The samples irradiation was realized in the research reactor TRIGA Mark III with a neutrons flow of 1centre dot10{sup 13}ncentre dotcm{sup -2}centre dots{sup -1}. The irradiation time was of 2 hours. Previous to the acquisition of the gamma rays spectrum the samples were allowed to decay from 12 to 14 days. The analyzed elements were: Nd, Ce, Lu, Eu, Yb, Pa(Th), Tb, La, Cr, Hf, Sc, Co, Fe, Cs, Rb. The statistical treatment of the data, consistent in the group analysis and the main components analysis allowed to identify three different origins of the archaeological ceramic, designated as: local, foreign and regional. (Author)

  1. Wide range neutron detection system

    International Nuclear Information System (INIS)

    Todt, W.H. Sr.

    1978-01-01

    A neutron detection system for reactor control is described which is operable over a wide range of neutron flux levels. The system includes a fission type ionization chamber neutron detector, means for gamma and alpha signal compensation, and means for operating the neutron detector in the pulse counting mode for low neutron flux levels, and in the direct current mode for high neutron flux levels

  2. Neutron monitoring for radiological protection

    International Nuclear Information System (INIS)

    Gibson, J.A.B.

    1985-01-01

    Neutron monitoring is a subject of increasing general interest and considerable attention is being paid to the development of improved techniques and methods for neutron monitoring. The Agency, therefore, considered it important to prepare a guide on the subject of neutron monitoring for radiation protection purposes. The present Manual is intended for those persons or authorities in Member States, particularly developing countries, who are responsible for the organization of neutron monitoring programmes and practical neutron monitoring. This Manual consequently, deals with topics such as neutron dosimetry, sources of neutrons and neutron detection as well as field instruments and operational systems used in this context

  3. Neutron spectroscopy, nuclear structure, related topics. Abstracts

    International Nuclear Information System (INIS)

    Sukhovoj, A.M.

    1996-01-01

    Neutron spectroscopy, nuclear structure and related topics are considered. P, T-breaking, neutron beta decay, neutron radiative capture and neutron polarizability are discussed. Reaction with fast neutrons, methodical aspect low-energy fission are considered too

  4. Laser neutron generator

    International Nuclear Information System (INIS)

    Anan'in, O.B.; Bespalov, D.F.; Bykovskii, Yu.A.; Kozyrev, Yu.P.; Mints, A.Z.; Riabov, E.V.; Tsybin, A.S.; Cherkasov, Yu.; Shikanov, A.E.

    1986-01-01

    Information is presented concerning devices for producing intense neutrons flows, and may be utilized in nuclear geophysics for carrying out pulsed neutron logging of wells, in studies of the critical characteristics of nuclear reactors, for activation analysis, radiation therapy, defectoscopy, and so on

  5. Muons, neutrons and superconductivity

    International Nuclear Information System (INIS)

    Aeppli, G.; Risoe National Lab., Roskilde

    1988-01-01

    The principles of the neutron scattering and muon spin relaxation (μSR) techniques and their applications to studies of superconductors are described briefly. μSR and neutron scattering work on magnetic correlations in superconductors and materials directly related to superconductors are reviewed. (orig.)

  6. Neutron resonance spectroscopy

    International Nuclear Information System (INIS)

    Gunsing, F.

    2005-06-01

    The present document has been written in order to obtain the diploma 'Habilitation a Diriger des Recherches'. Since this diploma is indispensable to supervise thesis students, I had the intention to write a document that can be useful for someone starting in the field of neutron resonance spectroscopy. Although the here described topics are already described elsewhere, and often in more detail, it seemed useful to have most of the relevant information in a single document. A general introduction places the topic of neutron-nucleus interaction in a nuclear physics context. The large variations of several orders of magnitude in neutron-induced reaction cross sections are explained in terms of nuclear level excitations. The random character of the resonances make nuclear model calculation predictions impossible. Then several fields in physics where neutron-induced reactions are important and to which I have contributed in some way or another, are mentioned in a first synthetic chapter. They concern topics like parity nonconservation in certain neutron resonances, stellar nucleosynthesis by neutron capture, and data for nuclear energy applications. The latter item is especially important for the transmutation of nuclear waste and for alternative fuel cycles. Nuclear data libraries are also briefly mentioned. A second chapter details the R-matrix theory. This formalism is the foundation of the description of the neutron-nucleus interaction and is present in all fields of neutron resonance spectroscopy. (author)

  7. Neutron resonance spectroscopy

    Energy Technology Data Exchange (ETDEWEB)

    Gunsing, F

    2005-06-15

    The present document has been written in order to obtain the diploma 'Habilitation a Diriger des Recherches'. Since this diploma is indispensable to supervise thesis students, I had the intention to write a document that can be useful for someone starting in the field of neutron resonance spectroscopy. Although the here described topics are already described elsewhere, and often in more detail, it seemed useful to have most of the relevant information in a single document. A general introduction places the topic of neutron-nucleus interaction in a nuclear physics context. The large variations of several orders of magnitude in neutron-induced reaction cross sections are explained in terms of nuclear level excitations. The random character of the resonances make nuclear model calculation predictions impossible. Then several fields in physics where neutron-induced reactions are important and to which I have contributed in some way or another, are mentioned in a first synthetic chapter. They concern topics like parity nonconservation in certain neutron resonances, stellar nucleosynthesis by neutron capture, and data for nuclear energy applications. The latter item is especially important for the transmutation of nuclear waste and for alternative fuel cycles. Nuclear data libraries are also briefly mentioned. A second chapter details the R-matrix theory. This formalism is the foundation of the description of the neutron-nucleus interaction and is present in all fields of neutron resonance spectroscopy. (author)

  8. Lunar neutron source function

    International Nuclear Information System (INIS)

    Kornblum, J.J.

    1974-01-01

    The search for a quantitative neutron source function for the lunar surface region is justified because it contributes to our understanding of the history of the lunar surface and of nuclear process occurring on the moon since its formation. A knowledge of the neutron source function and neutron flux distribution is important for the interpretation of many experimental measurements. This dissertation uses the available pertinent experimental measurements together with theoretical calculations to obtain an estimate of the lunar neutron source function below 15 MeV. Based upon reasonable assumptions a lunar neutron source function having adjustable parameters is assumed for neutrons below 15 MeV. The lunar neutron source function is composed of several components resulting from the action of cosmic rays with lunar material. A comparison with previous neutron calculations is made and significant differences are discussed. Application of the results to the problem of lunar soil histories is examined using the statistical model for soil development proposed by Fireman. The conclusion is drawn that the moon is losing mass

  9. Neutron Multiplicity Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Frame, Katherine Chiyoko [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-06-28

    Neutron multiplicity measurements are widely used for nondestructive assay (NDA) of special nuclear material (SNM). When combined with isotopic composition information, neutron multiplicity analysis can be used to estimate the spontaneous fission rate and leakage multiplication of SNM. When combined with isotopic information, the total mass of fissile material can also be determined. This presentation provides an overview of this technique.

  10. Applications of polarized neutrons

    International Nuclear Information System (INIS)

    Mezei, F.

    1993-01-01

    The additional spin degree of freedom of the neutron can be made use of in neutron scattering work in two fundamental ways: (a) directly for the identification of magnetic scattering effects and (b) indirectly as a spectroscopic tool for modulating and analysing beams. Although strong magnetic scattering contributions can often be studied by unpolarized neutrons, a fully unambiguous separation of nuclear and magnetic phenomena can only be achieved by the additional information provided by polarized neutrons, especially if one of the two kinds of contributions is weak compared to the other. In the most general case a sample with both magnetic and nuclear features can be characterized by as many as 16 independent dynamic correlation functions instead of the single well known S(q, ω) for non-magnetic nuclear scattering only. Polarization analysis in principle allows one to determine all these 16 functions. The indirect applications of polarized neutrons are also steadily gaining importance. The most widely used method of this kind, the application of Larmor precessions for high resolution energy analysis in Neutron Spin Echo spectroscopy opened up a whole new domain in inelastic neutron scattering which was not accessible to any other spectroscopic method with or without neutrons before. (author)

  11. Symposium on neutron scattering

    International Nuclear Information System (INIS)

    Lehmann, M.S.; Saenger, W.; Hildebrandt, G.; Dachs, H.

    1984-01-01

    Extended abstracts of the named symposium are presented. The first part of this report contains the abstracts of the lectures, the second those of the posters. Topics discussed on the symposium include neutron diffraction and neutron scattering studies in magnetism, solid state chemistry and physics, materials research. Some papers discussing instruments and methods are included too. (GSCH)

  12. filled neutron detectors

    Indian Academy of Sciences (India)

    Boron trifluoride (BF3) proportional counters are used as detectors for thermal neutrons. They are characterized by high neutron sensitivity and good gamma discriminating properties. Most practical BF3 counters are filled with pure boron trifluoride gas enriched up to 96% 10B. But BF3 is not an ideal proportional counter ...

  13. Mathematical methods in neutronics

    International Nuclear Information System (INIS)

    Planchard, J.

    1995-01-01

    This book presents the mathematical theory of nuclear reactors. It applies to engineers in neutronics and applied mathematicians. After a recall of the elementary notions of neutronics and of diffusion-type partial derivative equations, the theory of reactors criticality calculation is described. (J.S.)

  14. Multidisc neutron velocity selector

    International Nuclear Information System (INIS)

    Rosta, L.; Zsigmond, Gy.; Farago, B.; Mezei, F.; Ban, K.; Perendi, J.

    1987-12-01

    The prototype of a velocity selector for neutron monochromatization in the 4-20 A wavelength range is presented. The theoretical background of the multidisc rotor system is given together with a description of the mechanical construction and electronic driving system. The first tests and neutron measurements prove easy handling and excellent parameters. (author) 6 refs.; 7 figs.; 2 tabs

  15. The advanced neutron source

    International Nuclear Information System (INIS)

    Hayter, J.B.

    1994-01-01

    The Advanced Neutron Source (ANS), slated for construction start in 1994, will be a multipurpose neutron research laboratory serving academic and industrial users in chemistry, biology, condensed matter physics, nuclear and fundamental physics, materials science and engineering, and many other fields. It will be centered on the world's highest flux neutron beam reactor, operating at 330 MW, with careful design integration between the neutron source and the experiment systems. Many instruments will be situated in low backgrounds at distances up to 80 m from the reactor, using neutron guides with tailored neutron optical coatings for beam transport. Apart from the many stations for neutron scattering research, specialized stations will also be provided for isotope separation on-line, experiments with liquid hydrogen targets, neutron optical techniques such as interferometry, activation analysis, depth profiling, and positron production. Careful consideration has been given to providing a good research environment for visiting scientists, including easy access to the experimental areas, while maintaining a highly secure nuclear facility. This paper will describe the reactor and experimental facilities and give some examples of the types of research for which ANS has been designed

  16. Compact neutron generator

    Science.gov (United States)

    Leung, Ka-Ngo; Lou, Tak Pui

    2005-03-22

    A compact neutron generator has at its outer circumference a toroidal shaped plasma chamber in which a tritium (or other) plasma is generated. A RF antenna is wrapped around the plasma chamber. A plurality of tritium ion beamlets are extracted through spaced extraction apertures of a plasma electrode on the inner surface of the toroidal plasma chamber and directed inwardly toward the center of neutron generator. The beamlets pass through spaced acceleration and focusing electrodes to a neutron generating target at the center of neutron generator. The target is typically made of titanium tubing. Water is flowed through the tubing for cooling. The beam can be pulsed rapidly to achieve ultrashort neutron bursts. The target may be moved rapidly up and down so that the average power deposited on the surface of the target may be kept at a reasonable level. The neutron generator can produce fast neutrons from a T-T reaction which can be used for luggage and cargo interrogation applications. A luggage or cargo inspection system has a pulsed T-T neutron generator or source at the center, surrounded by associated gamma detectors and other components for identifying explosives or other contraband.

  17. Development of Neutron Spectrometer

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Hee; Lee, J. S.; Seong, B. S. (and others)

    2007-06-15

    Neutron spectrometers which are used in the basic researches such as physics, chemistry and materials science and applied in the industry were developed at the horizontal beam port of HANARO reactor. In addition, the development of core components for neutron scattering and the upgrade of existing facilities are also performed. The vertical neutron reflectometer was fabricated and installed at ST3 beam port. The performance test of the reflectometer was completed and the reflectometer was opened to users. The several core parts and options were added in the polarized neutron spectrometer. The horizontal neutron reflectometer from Brookhaven National Laboratory was moved to HANARO and installed, and the performance of the reflectometer was examined. The HIPD was developed and the performance test was completed. The base shielding for TAS was fabricated. The soller collimator, Cu mosaic monochromator, Si BPC monochromator and position sensitive detector were developed and applied in the neutron spectrometer as part of core component development activities. In addition, the sputtering machine for mirror device are fabricated and the neutron mirror is made using the sputtering machine. The FCD was upgraded and the performance of the FCD are improved over the factor of 10. The integration and upgrade of the neutron detection system were also performed.

  18. Synovectomy by Neutron capture

    International Nuclear Information System (INIS)

    Vega C, H.R.; Torres M, C.

    1998-01-01

    The Synovectomy by Neutron capture has as purpose the treatment of the rheumatoid arthritis, illness which at present does not have a definitive curing. This therapy requires a neutron source for irradiating the articulation affected. The energy spectra and the intensity of these neutrons are fundamental since these neutrons induce nuclear reactions of capture with Boron-10 inside the articulation and the freely energy of these reactions is transferred at the productive tissue of synovial liquid, annihilating it. In this work it is presented the neutron spectra results obtained with moderator packings of spherical geometry which contains in its center a Pu 239 Be source. The calculations were realized through Monte Carlo method. The moderators assayed were light water, heavy water base and the both combination of them. The spectra obtained, the average energy, the neutron total number by neutron emitted by source, the thermal neutron percentage and the dose equivalent allow us to suggest that the moderator packing more adequate is what has a light water thickness 0.5 cm (radius 2 cm) and 24.5 cm heavy water (radius 26.5 cm). (Author)

  19. Neutron filters for producing monoenergetic neutron beams

    International Nuclear Information System (INIS)

    Harvey, J.A.; Hill, N.W.; Harvey, J.R.

    1982-01-01

    Neutron transmission measurements have been made on high-purity, highly-enriched samples of 58 Ni (99.9%), 60 Ni (99.7%), 64 Zn (97.9%) and 184 W (94.5%) to measure their neutron windows and to assess their potential usefulness for producing monoenergetic beams of intermediate energies from a reactor. Transmission measurements on the Los Alamos Sc filter (44.26 cm Sc and 1.0 cm Ti) have been made to determine the characteristics of the transmitted neutron beam and to measure the total cross section of Sc at the 2.0 keV minimum. When corrected for the Ti and impurities, a value of 0.35 +- 0.03 b was obtained for this minimum

  20. Neutron Stars and Pulsars

    CERN Document Server

    Becker, Werner

    2009-01-01

    Neutron stars are the most compact astronomical objects in the universe which are accessible by direct observation. Studying neutron stars means studying physics in regimes unattainable in any terrestrial laboratory. Understanding their observed complex phenomena requires a wide range of scientific disciplines, including the nuclear and condensed matter physics of very dense matter in neutron star interiors, plasma physics and quantum electrodynamics of magnetospheres, and the relativistic magneto-hydrodynamics of electron-positron pulsar winds interacting with some ambient medium. Not to mention the test bed neutron stars provide for general relativity theories, and their importance as potential sources of gravitational waves. It is this variety of disciplines which, among others, makes neutron star research so fascinating, not only for those who have been working in the field for many years but also for students and young scientists. The aim of this book is to serve as a reference work which not only review...

  1. Fast neutrons dosimetry

    International Nuclear Information System (INIS)

    Rzyski, B.M.

    1977-01-01

    A proton recoil technique has been developed for inducing thermoluminescence with incident fast neutrons. CaF 2 was used as the TL phosphor, and cane sugar and polyethylene were used as proton radiators. The phosphor and the hydrogeneous material powders were well mixed, encapsulated in glass tubes and exposed to Am-Be sources, resulting in recoils from incident fast neutrons of energy between 0,25 and 11,25 MeV. The intrinsic response of pure CaF 2 to fast neutrons without a hydrogeneous radiator was checked by using LiF (TLD-700). Glow curves were recorded from room temperature up to 350 0 C after different doses of neutrons and gamma rays of 60 Co. First collision dose due to fast neutrons in tissue like materials such as cane sugar and polyethylene was also calculated [pt

  2. Diffuse scattering of neutrons

    International Nuclear Information System (INIS)

    Novion, C.H. de.

    1981-02-01

    The use of neutron scattering to study atomic disorder in metals and alloys is described. The diffuse elastic scattering of neutrons by a perfect crystal lattice leads to a diffraction spectrum with only Bragg spreads. the existence of disorder in the crystal results in intensity and position modifications to these spreads, and above all, to the appearance of a low intensity scatter between Bragg peaks. The elastic scattering of neutrons is treated in this text, i.e. by measuring the number of scattered neutrons having the same energy as the incident neutrons. Such measurements yield information on the static disorder in the crystal and time average fluctuations in composition and atomic displacements [fr

  3. A Neutron Rem Counter

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, I Oe; Braun, J

    1964-01-15

    A neutron detector is described which measures the neutron dose rate in rem/h independently of the energy of the neutrons from thermal to 15 MeV. The detector consists of a BF{sub 3} proportional counter surrounded by a shield made of polyethylene and boron plastic that gives the appropriate amount of moderation and absorption to the impinging neutrons to obtain rem response. Two different versions have been developed. One model can utilize standard BF{sub 3} counters and is suitable for use in installed monitors around reactors and accelerators and the other model is specially designed for use in a portable survey instrument. The neutron rem counter for portable instruments has a sensitivity of 2.4 cps/mrem/h and is essentially nondirectional in response. With correct bias setting the counter is insensitive to gamma exposure up to 200 r/h from Co-60.

  4. Simulated workplace neutron fields

    International Nuclear Information System (INIS)

    Lacoste, V.; Taylor, G.; Rottger, S.

    2011-01-01

    The use of simulated workplace neutron fields, which aim at replicating radiation fields at practical workplaces, is an alternative solution for the calibration of neutron dosemeters. They offer more appropriate calibration coefficients when the mean fluence-to-dose equivalent conversion coefficients of the simulated and practical fields are comparable. Intensive Monte Carlo modelling work has become quite indispensable for the design and/or the characterization of the produced mixed neutron/photon fields, and the use of Bonner sphere systems and proton recoil spectrometers is also mandatory for a reliable experimental determination of the neutron fluence energy distribution over the whole energy range. The establishment of a calibration capability with a simulated workplace neutron field is not an easy task; to date only few facilities are available as standard calibration fields. (authors)

  5. Neutron PSDs for the next generation of spallation neutron sources

    CERN Document Server

    Eijk, C W

    2002-01-01

    A review of R and D for neutron PSDs to be used at anticipated new spallation neutron sources: the Time-of-Flight system facility, European Spallation Source, Spallation Neutron Source and Neutron Arena, is presented. The gas-filled detectors, scintillation detectors and hybrid systems are emphasized.

  6. Fail-safe neutron shutter used for thermal neutron radiography

    International Nuclear Information System (INIS)

    Sachs, R.D.; Morris, R.A.

    1976-11-01

    A fail-safe, reliable, easy-to-use neutron shutter was designed, built, and put into operation at the Omega West Reactor, Los Alamos Scientific Laboratory. The neutron shutter will be used primarily to perform thermal neutron radiography, but is also available for a highly collimated source of thermal neutrons [neutron flux = 3.876 x 10 6 (neutrons)/(cm 2 .s)]. Neutron collimator sizes of either 10.16 by 10.16 cm or 10.16 by 30.48 cm are available

  7. Neutron optics using transverse field neutron spin echo method

    International Nuclear Information System (INIS)

    Achiwa, Norio; Hino, Masahiro; Yamauchi, Yoshihiro; Takakura, Hiroyuki; Tasaki, Seiji; Akiyoshi, Tsunekazu; Ebisawa, Toru.

    1993-01-01

    A neutron spin echo (NSE) spectrometer with perpendicular magnetic field to the neutron scattering plane, using an iron yoke type electro-magnet has been developed. A combination of cold neutron guider, supermirror neutron polarizer of double reflection type and supermirror neutron analyser was adopted for the spectrometer. The first application of the NSE spectrometer to neutron optics by passing Larmor precessing neutrons through gas, solid and liquid materials of several different lengths which are inserted in one of the precession field have been examined. Preliminary NSE spectra of this sample geometry are discussed. (author)

  8. A Double Slow Neutron Spectrometer; Spectrometre double pour neutrons lents; Dvojnoj spektrometr medlennykh nejtronov; Espectrometro doble para neutrones lentos

    Energy Technology Data Exchange (ETDEWEB)

    Bondarenko, I I; Liforov, V G; Nikolaev, M N; Orlov, V V; Parfenov, V A; Semenov, V A; Smirnov, V I; Turchin, V F [Fehi, Moscow, SSSR (Russian Federation)

    1963-01-15

    spectrometre et donnent des indications precises sur ses caracteristiques. (author) [Spanish] Los autores describen un espectrometro neutronico destinado a la medicion de las distribuciones energeticas y angulares de neutrones monocromaticos lentos, dispersados inelasticamente en Iliquidos y solidos. Los experimentos de esa indole permiten obtener informacion detallada sobre la dinamica de los atomos en distintos estados de agregacion de la materia. El espectrometro se basa en la medida del tiempo de vuelo. Como fuente pulsante de neutrones se emplea el reactor IBR-1. Actua como monocromador un interruptor mecanico, que gira sincronicamente con el disco del reactor IBR con uen defasaje prefijado. Mediante un sistema especial de regulacion se obtiene una estabilidad de fase superior a 0,5{sup o}. Los neutrones dispersados por la probeta se registran con un detector de centelleo colocado en un angulo determinado con relacion al haz neutronico. Bi poder de resolucion del espectrometro es del orden de los 15 {mu}s/m. Los autores describen en detalle la construccion del espectrometro y proporcionan indicaciones precisas sobre sus caracteristicas. (author)

  9. Determination of Ca, Cr, Cu, Fe, K, Mg, Na and Zn in Brazilian medicinal plants by neutron activation and atomic absorption; Determinacao de Ca, Cr, Cu, Fe, K, Mg, Na e Zn em plantas medicinais brasileiras por ativacao neutronica e absorcao atomica

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Ricardo P. de; Sabino, Claudia de Vilhena S.; Franco, Milton B.; Amaral, Angela M.; Guedes, Joao B.; Assis, Adilson de C. [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil); Leite, Simone C.A.L.; Silva, Isabel R. [Pontificia Univ. Catolica de Minas Gerais, Belo Horizonte, MG (Brazil)

    2002-07-01

    Medicinal plants are available in the markets in Belo Horizonte, Minas Gerais. The objective of this work is to investigate the Ca, Cr, Cu, Fe, K, Mg, Na e Zn concentrations in two lots of usually known diuretics plants (azeitona do mato, cabelo de milho, cavalinha, cervejinha do campo, chapeu de couro, congonha de bugre, marmelinho do campo and quebra pedra) bought with an interval of time - six months - between the purchases. The elemental concentrations were determined applying k{sub 0} instrumental neutron activation analysis and atomic absorption spectrophotometry analysis. (author)

  10. Porøse materialer

    DEFF Research Database (Denmark)

    Hansen, Ernst Jan de Place

    2000-01-01

    Dette undervisningsnotat er en samling af noter, der refererer til den indledende del af kurset Materialmekanik og Porøse materailer på Insitut for Bærende Konstruktiner og Materialer (BKM).......Dette undervisningsnotat er en samling af noter, der refererer til den indledende del af kurset Materialmekanik og Porøse materailer på Insitut for Bærende Konstruktiner og Materialer (BKM)....

  11. Neutron flux monitor

    International Nuclear Information System (INIS)

    Oda, Naotaka.

    1993-01-01

    The device of the present invention greatly saves an analog processing section such as an analog filter and an analog processing circuit. That is, the device of the present invention comprises (1) a neutron flux detection means for detecting neutron fluxed in the reactor, (2) a digital filter means for dividing signals corresponding to the detected neutron fluxes into predetermined frequency band regions, (3) a calculation processing means for applying a calculation processing corresponding to the frequency band regions to the neutron flux detection signals divided by the digital filter means. With such a constitution, since the neutron detection signals are processed by the digital filter means, the accuracy is improved and the change for the property of the filter is facilitated. Further, when a neutron flux level is obtained, a calculation processing corresponding to the frequency band region can be conducted without the analog processing circuit. Accordingly, maintenance and accuracy are improved by greatly decreasing the number of parts. Further, since problems inherent to the analog circuit are solved, neutron fluxes are monitored at high reliability. (I.S.)

  12. Neutron Science 21

    International Nuclear Information System (INIS)

    Park, Sung Il; Choi, Yong Nam; Ahn, Geun Young; Lee, Hee Joo; Hong, Ji Sun; Kim, Hyo Sun

    2009-01-01

    The project aims to make the HANARO neutron beam facility a neutron research hub in the Asia-Pacific. This is a part of the effort to make the facility as productive as other neutron beam facilities in America and Europe which already operate as a hub that attracts thousands of users and produces hundreds of publications annually. The projects promotes 1) collaborative research between HANARO personnel and users, 2) internationally collaboration on various fronts of neutron science related activities. To achieve the above in an effective manner, its direction is adjusted by a series of meetings and the activities of the project are advertised to the public media. 3 domestic and 1 international collaborative research was carried out successfully in 2008 by using the HRPD. The 1st Asia-Oceania Neutron Summer School was successfully hosted in Korea. The annual report of the HANARO neutron beam facility was published. 3 advisory meetings and 6 internal meetings to promote the hub were held. Users were surveyed on their needs. The media was contacted twice in an effort to advertise the project activities. All of the above achievements are directly applicable to determining the national policy on neutron science. It is advised that the KAERI management take notice of the results to manage the facility effectively

  13. Neutrons at COSY

    International Nuclear Information System (INIS)

    Filges, D.; Freiesleben, H.

    1988-05-01

    For many years neutrons were considered important both as a useful probe in nuclear physics research and as an initiator and catalyst for fission, fusion and other applications. As a result knowledge about neutrons, especially below 20 MeV, received organized world-wide attention. Research with neutrons at medium energies, say 50 MeV to several GeV, has not consistently received attention and no systematic evaluations exist. But there is a large and considerable interest today because medium energy neutrons are very important in basic science and technology. The aim of this workshop was to provide an overview of the present status and the research which should be carried out in this field in future and which kind of experiments should be performed at the COSY facility: State-of-the-art about medium energy neutron experiments and existing facilities; planned experiments; needs for experiments doing research with neutrons at COSY (detectors, accelerator requirements, time structure etc.); what will be a first experiment to measure neutrons at COSY. The interest in this workshop is documented by a large number of participants. Copies of the viewgraphs of the talks are provided. (orig./HP)

  14. Neutron generation in lightning bolts

    International Nuclear Information System (INIS)

    Shah, G.N.; Razdan, H.; Bhat, C.L.; Ali, Q.M.

    1985-01-01

    To ascertain neutron generation in lightning bolts, the authors have searched for neutrons from individual lightning strokes, for a time-interval comparable with the duration of the lightning stroke. 10 7 -10 10 neutrons per stroke were found, thus providing the first experimental evidence that neutrons are generated in lightning discharges. (U.K.)

  15. Neutron Electric Dipole Moment Experiments

    OpenAIRE

    Peng, Jen-Chieh

    2008-01-01

    The neutron electric dipole moment (EDM) provides unique information on CP violation and physics beyond the Standard Model. We first review the history of experimental searches for neutron electric dipole moment. The status of future neutron EDM experiments, including experiments using ultra-cold neutrons produced in superfluid helium, will then be presented.

  16. Basic research of neutron radiography using cold neutron beam

    International Nuclear Information System (INIS)

    Oda, Masahiro; Tamaki, Masayoshi; Tasaka, Kanji

    1995-01-01

    As the result of demanding high quality images, now the nuclear reactors which can supply stably intense neutron beam have become the most general neutron source for radiography. For the purpose, mostly thermal neutrons have been used, but it is indispensable to use other neutrons than thermal neutrons for advancing neutron radiography technology and expanding the application fields. The radiography using cold neutrons is most behind in the development because the suitable neutron source was not available in Japan. The neutron sources for exclusively obtaining intense cold neutron beam were installed in the Kyoto University reactor in 1986 and in the JRR-3M of Japan Atomic Energy Research Institute in 1991. Basically as neutron energy lowers, the cross section of substances increases. In certain crystalline substances, the Bragg cutoff arises. The removal of scattered neutrons, the measurement of parallelism of beam and the relation of the thickness of objects with the transmissivity of cold neutrons are described. The imaging by TV method and the cold neutron CT in the CNRF and the simplified neutron CT by film method are reported. (K.I.)

  17. Double beam neutron radiography facility

    International Nuclear Information System (INIS)

    Domanus, J.C.

    1977-09-01

    The DR1 reactor at Risoe is used as a neutron source for neutron radiography. In the double-beam neutron radiography facility a neutron flux of an intensity of 1.4 and 1.8 x 10 6 n. cm -2 . s -1 reaches the object to be radiographed. The transport and exposure container used for neutron radiography of irradiated nuclear fuel rods is described, and the exposure technique and procedure are reviewed. The mode by which single neutron radiographs are assembled and assessed is described. This report will be published in the ''Neutron Radiography Newsletter''. (author)

  18. Thermal neutron source study

    International Nuclear Information System (INIS)

    Holden, T.M.

    1983-05-01

    The value of intense neutron beams for condensed matter research is discussed with emphasis on the complementary nature of steady state and pulsed neutron sources. A large body of information on neutron sources, both existing and planned, is then summarized under four major headings: fission reactors, electron accelerators with heavy metal targets, pulsed spallation sources and 'steady state' spallation sources. Although the cost of a spallation source is expected to exceed that of a fission reactor of the same flux by a factor of two, there are significant advantages for a spallation device such as the proposed Electronuclear Materials Test Facility (EMTF)

  19. Virtual neutron scattering experiments

    DEFF Research Database (Denmark)

    Overgaard, Julie Hougaard; Bruun, Jesper; May, Michael

    2017-01-01

    . In the last week of the course, students travel to a large-scale neutron scattering facility to perform real neutron scattering experiments. Through student interviews and survey answers, we argue, that the virtual training prepares the students to engage more fruitfully with experiments by letting them focus......We describe how virtual experiments can be utilized in a learning design that prepares students for hands-on experiments at large-scale facilities. We illustrate the design by showing how virtual experiments are used at the Niels Bohr Institute in a master level course on neutron scattering...

  20. Fruits of neutron research

    International Nuclear Information System (INIS)

    Krause, C.

    1994-01-01

    Car windshields that don't break during accidents and jets that fly longer without making a refueling stop. Compact discs, credit cards, and pocket calculators. Refrigerator magnets and automatic car window openers. Beach shoes, food packaging, and bulletproof vests made of tough plastics. The quality and range of consumer products have improved steadily since the 1970s. One of the reasons: neutron research. Industries, employing neutron scattering techniques, to study materials properties, to act as diagnostics in tracing system performance, or as sources for radioactive isotopes used in medical fields for diagnostics or treatment, have all benefited from the fruits of advanced work with neutron sources

  1. Deep inelastic neutron scattering

    International Nuclear Information System (INIS)

    Mayers, J.

    1989-03-01

    The report is based on an invited talk given at a conference on ''Neutron Scattering at ISIS: Recent Highlights in Condensed Matter Research'', which was held in Rome, 1988, and is intended as an introduction to the techniques of Deep Inelastic Neutron Scattering. The subject is discussed under the following topic headings:- the impulse approximation I.A., scaling behaviour, kinematical consequences of energy and momentum conservation, examples of measurements, derivation of the I.A., the I.A. in a harmonic system, and validity of the I.A. in neutron scattering. (U.K.)

  2. Coupled moderator neutronics

    International Nuclear Information System (INIS)

    Russell, G.J.; Pitcher, E.J.; Ferguson, P.D.

    1995-01-01

    Optimizing the neutronic performance of a coupled-moderator system for a Long-Pulse Spallation Source is a new and challenging area for the spallation target-system designer. For optimal performance of a neutron source, it is essential to have good communication with instrument scientists to obtain proper design criteria and continued interaction with mechanical, thermal-hydraulic, and materials engineers to attain a practical design. A good comprehension of the basics of coupled-moderator neutronics will aid in the proper design of a target system for a Long-Pulse Spallation Source

  3. Fission neutron multiplicity calculations

    International Nuclear Information System (INIS)

    Maerten, H.; Ruben, A.; Seeliger, D.

    1991-01-01

    A model for calculating neutron multiplicities in nuclear fission is presented. It is based on the solution of the energy partition problem as function of mass asymmetry within a phenomenological approach including temperature-dependent microscopic energies. Nuclear structure effects on fragment de-excitation, which influence neutron multiplicities, are discussed. Temperature effects on microscopic energy play an important role in induced fission reactions. Calculated results are presented for various fission reactions induced by neutrons. Data cover the incident energy range 0-20 MeV, i.e. multiple chance fission is considered. (author). 28 refs, 13 figs

  4. Neutron irradiation therapy machine

    International Nuclear Information System (INIS)

    1980-01-01

    Conventional neutron irradiation therapy machines, based on the use of cyclotrons for producing neutron beams, use a superconducting magnet for the cyclotron's magnetic field. This necessitates complex liquid He equipment and presents problems in general hospital use. If conventional magnets are used, the weight of the magnet poles considerably complicates the design of the rotating gantry. Such a therapy machine, gantry and target facilities are described in detail. The use of protons and deuterons to produce the neutron beams is compared and contrasted. (U.K.)

  5. Advanced neutron source project

    International Nuclear Information System (INIS)

    Gorynina, L.V.; Proskuryakov, S.F.; Tishchenko, V.A.; Uzhanova, V.V.

    1991-01-01

    The project of the ANS improved neutron source intended for fundamental researches in nuclear physics and materials testing is considered. New superhigh-flux heavy-water 350 MW reactor is used for the source creation. The standard fuel is uranium silicide (U 3 Si 2 ). Reactor core volume equals 67.4 l and average power density is 4.9 MW/l. Neutron flux density is 10 16 neutron/(cm 2 xs). The facility construction begin is planned for 1996. The first experiments should be accomplished in 2000

  6. Reproducibility of the new automatic sample changer coupled to the gamma spectrometer as support for Neutronic Activation Analysis; Reprodutibilidade do novo trocador automático de amostras acoplado a espectrômetro gama como suporte à análise por ativação neutrônica

    Energy Technology Data Exchange (ETDEWEB)

    Venancio, Raoni J.M.; Menezes, Maria Ângela de B.C.; Dutra Neto, Aimoré, E-mail: raonirjv@hotmail.com, E-mail: raoni.venancio@cdtn.br, E-mail: menezes@cdtn.br, E-mail: dutraa@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    Aiming to optimize and make the analyzes in gamma spectrometry more efficient, an automatic sample changer was recently developed for the gamma spectrometry step of the neutron activation analysis and was installed in the CDTN / CNEN Neutron Activation Laboratory. Usually, the exchange of samples in gamma spectrometry is performed manually, that is, it depends on an operator to perform the sample exchange. However, it is known that the manual exchange of the samples presents some setbacks, such as the low yield of the number of samples analyzed due to non-use in atypical schedules. The development of a system that exchanged samples regardless of date and time would solve these problems. Thus, an automatic sample exchange system has been developed that is connected to one of the laboratory's gamma spectrometers. The exchanger should replace the step that is performed manually. In order to evaluate whether the automatic exchanger will perform the swapping of samples correctly, preliminary tests were performed to verify the reproducibility of the system and consequently the stability of the results obtained. The tests already carried out were conducted under the normal operating conditions of the system, in order to present results that are closer to reality. The results showed that the system is working properly.

  7. Optimization of instrumental neutron activation analysis for the within-bottle homogeneity study of reference materials of marine origin; Otimização da análise por ativação neutrônica instrumental para o estudo de homogeneidade dentro do frasco de materiais de referência de origem marinha

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Daniel Pereira da

    2017-07-01

    The use of reference materials has been increasing in chemical analysis laboratories as its use is important for measurement validation in analytical chemistry. Such materials are generally imported, which require high financial investments in order to acquire them, and therefore it impacts on the difficulty to many national laboratories to use reference materials in their chemical analysis routine. Certification of reference materials is a complex process that assumes that the user is given appropriate assigned values of the properties of interests in the material. In this process, the homogeneity of the material must be checked. In this study, the within-bottle homogeneity study for the elements K, Mg, Mn, Na and V was performed for two reference materials of marine origin: the mussel reference material produced at the Neutron Activation Laboratory (LAN) of IPEN - CNEN/SP and an oyster tissue reference material produced abroad. For this purpose, the elements were determined in subsamples with masses varying between 1 and 250 mg by Instrumental Neutron Activation Analysis (INAA) and minimum sample intakes were estimated, ranging from 0.015 g for Na in the mussel reference material to 0.100 g for V in the two reference materials. (author)

  8. Analysis of the elementary composition of the phytoterapics Espinheira Santa and eggplant by the method of Neutron Activation Analysis; Análise da composição elementar dos fitoterápicos espinheira santa e berinjela pelo método de análise por ativação com nêutrons

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Luan M.; Saiki, Mitiko, E-mail: luan.pereira@usp.br, E-mail: mitiko@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    The use of herbal medicines has become quite popular in Brazil due to its vast flora and the belief that everything that is natural does not present harmful effects to human health. However, these products may contain toxic or excessively harmful to the human organism. The objective of this work was to analyze herbal medicine Espinheira Santa (Maytenus ilicifolia) and Eggplant (Solanum melongena) by the method of neutron activation analysis (NAA). Phytotherapeutic samples were obtained from drugstores in the form of capsules, and their contents were removed from the capsules for analysis. The NAA procedure consisted of irradiate phytotherapeutic aliquots and the synthetic neutron element patterns of the nuclear reactor IEAR-1 followed by gamma-ray spectrometry. The radioisotopes formed were identified by half lives and gamma ray energies and the concentrations of the elements were calculated by the comparative method. For analytical quality control, the certified reference materials were analyzed and the results presented good accuracy and precision. In the phytoterapics, the elements K and Ca were found in higher concentrations, in the order of mg g{sup -1}, Br, Fe, Rb and Zn of the order of μg g{sup -1} and the elements Co, Cr, Cs, La and Sc of the order of ng g{sup -1}. Results obtained in this work demonstrated the feasibility of applying the NAA procedure in the determination of the elemental composition of phytoterapics.

  9. A Cold Neutron Monochromator and Scattering Apparatus; Monochromateur et appareillage pour la diffusion de neutrons lents; Monokhromator dlya ''kholodnykh'' nejtronov i pribor dlya rasseyaniya; Monocromador y aparato de dispersion para neutrones frios

    Energy Technology Data Exchange (ETDEWEB)

    Harris, D; Cocking, S J; Egelstaff, P A; Webb, F J [Nuclear Physics Division, Aere, Harwell, Didcot, Berks (United Kingdom)

    1963-01-15

    . Finalement, un rotor a rainures courbes en magnesium et cadmium, ayant une vitesse de rotation elevee, les laisse passer par bouffees. Dans cet appareil, le filtre Be-Bi sert a determiner la dispersion de la longueur d'onde (comprise entre 0,3 A et 4,1 A) et le rotor, la dispersion en fonction du temps (8 {mu}s). Les bouffees de neutrons monochromatiques provenant du rotor sont diffusees par un echantillon et detectees dans l'une de deux series de compteurs. Lorsqu'on etudie des echantillons liquides ou polycristallins, on emploie une serie de compteurs BF{sub 3} (dimensions: 2 x 2 4 pouces) couvrant des angles de diffusion variant de 20{sup o} a 90{sup o}. Cette serie est placee en-dessous du faisceau de neutrons. Au-dessus de l'axe du faisceau neutronique se trouve la deuxieme serie comprenant trois scintillateurs (diametre 2 pouces) pour etudier des echantillons de monocristaux. Chaque compteur agit sur un systeme d'enregistrement a bande magnetique qui comporte 500 canaux utilisables pour chacun des compteurs. Les auteurs se sont servis de cet appareil pour etudier la diffusion des neutrons dans plusieurs echantillons gazeux, liquides et cristallins. Dans d'autres memoires presentes au Colloque ils donnent les resultats des dernieres mesures faites. (author) [Spanish] De un haz colimado de neutrones, emitido por el reactor Dido de Harwell, se selecciona una estrecha banda de longitudes de onda neutronicas (4 A y mayores). Estos neutrones son dispersados por varias muestras y la energia por ellos cedida se mide segun el metodo del tiempo de vuelo. Los neutrones, moderados por una fuente de hidrogeno liquido situada en el reactor, atraviesan primero un filtro refrigerado por nitrogeno liquido, seguidamente un monocristal de bismuto, siendo, por ultimo ''interceptados'' por un rotor de ranura curva, de magnesio-cadmio animado de gran velocidad. En este aparato el ensanchamiento de longitud de onda (0, 3A a 4,1 A) queda principalmente determinado por el filtro de Be-Bi, y el

  10. Neutron spectra produced by moderating an isotopic neutron source

    International Nuclear Information System (INIS)

    Carrillo Nunnez, Aureliano; Vega Carrillo, Hector Rene

    2001-01-01

    A Monte Carlo study has been carried out to determine the neutron spectra produced by an isotopic neutron source inserted in moderating media. Most devices used for radiation protection have a response strongly dependent on neutron energy. ISO recommends several neutron sources and monoenergetic neutron radiations, but actual working situations have broad spectral neutron distributions extending from thermal to MeV energies, for instance, near nuclear power plants, medical applications accelerators and cosmic neutrons. To improve the evaluation of the dosimetric quantities, is recommended to calibrate the radiation protection devices in neutron spectra which are nearly like those met in practice. In order to complete the range of neutron calibrating sources, it seems useful to develop several wide spectral distributions representative of typical spectra down to thermal energies. The aim of this investigation was to use an isotopic neutron source in different moderating media to reproduce some of the neutron fields found in practice. MCNP code has been used during calculations, in these a 239PuBe neutron source was inserted in H2O, D2O and polyethylene moderators. Moderators were modeled as spheres and cylinders of different sizes. In the case of cylindrical geometry the anisotropy of resulting neutron spectra was calculated from 0 to 2 . From neutron spectra dosimetric features were calculated. MCNP calculations were validated by measuring the neutron spectra of a 239PuBe neutron source inserted in a H2O cylindrical moderator. The measurements were carried out with a multisphere neutron spectrometer with a 6LiI(Eu) scintillator. From the measurements the neutron spectrum was unfolded using the BUNKIUT code and the UTA4 response matrix. Some of the moderators with the source produce a neutron spectrum close to spectra found in actual applications, then can be used during the calibration of radiation protection devices

  11. Neutron Depolarization in Superconductors

    Science.gov (United States)

    Zhuchenko, N. K.

    1995-04-01

    The dependences of neutron depolarization on applied magnetic field are deduced along the magnetization hysteresis loop in terms of the Bean model of the critical state. The depolarization in uniaxial superconductors with the reversible magnetization, including uniaxial magnetic superconductors, is also considered. A strong depolarization is expected if the neutrons travel along the vortex lines. On calcule la dépendance en champ magnétique de la dépolarisation des neutrons le long du cycle d'hystérésis en termes du modèle critique de Bean. On considère aussi la dépolarisation dans les supraconducteurs uniaxiaux en fonction de l'aimantation réversible, y compris pour les supraconducteurs magnétiques. On attend une forte dépolarisation si les neutrons se propagent le long des vortex.

  12. Scattering with polarized neutrons

    International Nuclear Information System (INIS)

    Schweizer, J.

    2007-01-01

    In the history of neutron scattering, it was shown very soon that the use of polarized neutron beams brings much more information than usual scattering with unpolarized neutrons. We shall develop here the different scattering methods that imply polarized neutrons: 1) polarized beams without polarization analysis, the flipping ratio method; 2) polarized beams with a uniaxial polarization analysis; 3) polarized beams with a spherical polarization analysis. For all these scattering methods, we shall give examples of the physical problems which can been solved by these methods, particularly in the field of magnetism: investigation of complex magnetic structures, investigation of spin or magnetization densities in metals, insulators and molecular compounds, separation of magnetic and nuclear scattering, investigation of magnetic properties of liquids and amorphous materials and even, for non magnetic material, separation between coherent and incoherent scattering. (author)

  13. Personnel neutron dosimetry

    International Nuclear Information System (INIS)

    Hankins, D.

    1982-04-01

    This edited transcript of a presentation on personnel neutron discusses the accuracy of present dosimetry practices, requirements, calibration, dosemeter types, quality factors, operational problems, and dosimetry for a criticality accident. 32 figs

  14. High energy neutron generator

    International Nuclear Information System (INIS)

    Barjon, R.; Breynat, G.

    1987-01-01

    This patent describes a generator of fast neutrons only slightly contaminated by neutrons of energy less than 15 MeV, comprising a source of charged particles of energy equal to at least 15 MeV, a target made of lithium deuteride, and means for cooling the target. The target comprises at least two elements placed in series in the path of the charged particles and separated from each other, the thickness of each of the elements being selected as a function of the average energy of the charged particles emitted from the source and the energy of the fast neutrons to be generated such that neutrons of energy equal to at least 15 MeV are emitted in the forward direction in response to the bombardment of the target from behind by the charged particles. The target cooling means comprises means for circulating between and around the elements a gas which does not chemically react with lithium deuteride

  15. The neutron computer tomography

    International Nuclear Information System (INIS)

    Matsumoto, G.; Krata, S.

    1983-01-01

    The method of computer tomography (CT) was applied for neutrons instead of X-rays. The neutron radiography image of samples was scanned by microphotometer to get the transmission data. This process was so time-consuming that the number of incident angles to samples could not be increased. The transmission data was processed by FACOM computer and CT image was gained. In the experiment at the Japan Research Reactor No. 4 at Tokai-mura with 18 projection angles, the resolution of paraffin in the aluminum block was less than 0.8 mm. In the experiment at Van de Graaf accelerator of Nagoya University, this same resolution was 1.2 mm because of the angle distribution of neutron beam. This experiment is the preliminary one, the facility which utilizes neutron television and video-recorder will be necessary for the next stage. (Auth.)

  16. Neutron dosimetry in biology

    International Nuclear Information System (INIS)

    Sigurbjoernsson, B.; Smith, H.H.; Gustafsson, A.

    1965-01-01

    To study adequately the biological effects of different energy neutrons it is necessary to have high-intensity sources which are not contaminated by other radiations, the most serious of which are gamma rays. An effective dosimetry must provide an accurate measure of the absorbed dose, in biological materials, of each type of radiation at any reactor facility involved in radiobiological research. A standardized biological dosimetry, in addition to physical and chemical methods, may be desirable. The ideal data needed to achieve a fully documented dosimetry has been compiled by H. Glubrecht: (1) Energy spectrum and intensity of neutrons; (2) Angular distribution of neutrons on the whole surface of the irradiated object; (3) Additional undesired radiation accompanying the neutrons; (4) Physical state and chemical composition of the irradiated object. It is not sufficient to note only an integral dose value (e.g. in 'rad') as the biological effect depends on the above data

  17. The intense neutron generator

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, W B

    1966-07-01

    The presentation discusses both the economic and research contexts that would be served by producing neutrons in gram quantities at high intensities by electrical means without uranium-235. The revenue from producing radioisotopes is attractive. The array of techniques introduced by the multipurpose 65 megawatt Intense Neutron Generator project includes liquid metal cooling, superconducting magnets for beam bending and focussing, super-conductors for low-loss high-power radiofrequency systems, efficient devices for producing radiofrequency power, plasma physics developments for producing and accelerating hydrogen, ions at high intensity that are still far out from established practice, a multimegawatt high voltage D.C. generating machine that could have several applications. The research fields served relate principally to materials science through neutron-phonon and other quantum interactions as well as through neutron diffraction. Nuclear physics is served through {mu}-, {pi}- and K-meson production. Isotope production enters many fields of applied research. (author)

  18. Neutron personnel dosimetry

    International Nuclear Information System (INIS)

    Griffith, R.V.

    1981-01-01

    The current state-of-the-art in neutron personnel dosimetry is reviewed. Topics covered include dosimetry needs and alternatives, current dosimetry approaches, personnel monitoring devices, calibration strategies, and future developments

  19. Neutron resonance averaging

    International Nuclear Information System (INIS)

    Chrien, R.E.

    1986-10-01

    The principles of resonance averaging as applied to neutron capture reactions are described. Several illustrations of resonance averaging to problems of nuclear structure and the distribution of radiative strength in nuclei are provided. 30 refs., 12 figs

  20. Neutron flux monitoring device

    International Nuclear Information System (INIS)

    Goto, Yasushi; Mitsubori, Minehisa; Ohashi, Kazunori.

    1997-01-01

    The present invention provides a neutron flux monitoring device for preventing occurrence of erroneous reactor scram caused by the elevation of the indication of a start region monitor (SRM) due to a factor different from actual increase of neutron fluxes. Namely, judgement based on measured values obtained by a pulse counting method and a judgment based on measured values obtained by a Cambel method are combined. A logic of switching neutron flux measuring method to be used for monitoring, namely, switching to an intermediate region when both of the judgements are valid is adopted. Then, even if the indication value is elevated based on the Cambel method with no increase of the counter rate in a neutron source region, the switching to the intermediate region is not conducted. As a result, erroneous reactor scram such as 'shorter reactor period' can be avoided. (I.S.)

  1. Neutron induced radiation damage

    International Nuclear Information System (INIS)

    Williams, M.M.R.

    1977-01-01

    We derive a general expression for the number of displaced atoms of type j caused by a primary knock-on of type i. The Kinchin-Pease model is used, but considerably generalised to allow for realistic atomic potentials. Two cases are considered in detail: the single particle problem causing a cascade and the neutron initiated problem which leads to multiple subcascades. Numerical results have been obtained for a variety of scattering laws. An important conclusion is that neutron initiated damage is much more severe than atom-initiated damage and leads to the number of displaced atoms being a factor of (A+1) 2 /4A larger than the single primary knock-on theory predicts. A is the ratio of the atomic mass to the neutron mass. The importance of this result to the theory of neutron sputtering is explained. (orig.) [de

  2. Directionally positionable neutron beam

    International Nuclear Information System (INIS)

    Dance, W.E.; Bumgardner, H.M.

    1981-01-01

    Disclosed is apparatus for forming and directionally positioning a neutron beam. The apparatus includes an enclosed housing rotatable about a first axis with a neutron source axially positioned on the axis of rotation of the enclosed housing but not rotating with the housing. The rotatable housing is carried by a vertically positionable arm carried on a mobile transport. A collimator is supported by the rotatable housing and projects into the housing to orientationally position its inlet window at an adjustably fixed axial and radial spacing from the neutron source so that rotation of the enclosed housing causes the inlet window to rotate about a circle which is a fixed axial distance from the neutron source and has the axis of rotation of the housing as its center. (author)

  3. Cylindrical neutron generator

    Science.gov (United States)

    Leung, Ka-Ngo [Hercules, CA

    2008-04-22

    A cylindrical neutron generator is formed with a coaxial RF-driven plasma ion source and target. A deuterium (or deuterium and tritium) plasma is produced by RF excitation in a cylindrical plasma ion generator using an RF antenna. A cylindrical neutron generating target is coaxial with the ion generator, separated by plasma and extraction electrodes which contain many slots. The plasma generator emanates ions radially over 360.degree. and the cylindrical target is thus irradiated by ions over its entire circumference. The plasma generator and target may be as long as desired. The plasma generator may be in the center and the neutron target on the outside, or the plasma generator may be on the outside and the target on the inside. In a nested configuration, several concentric targets and plasma generating regions are nested to increase the neutron flux.

  4. Neutron-absorbing alloys

    International Nuclear Information System (INIS)

    Portnoi, K.I.; Arabei, L.B.; Gryaznov, G.M.; Levi, L.I.; Lunin, G.L.; Kozhukhov, V.M.; Markov, J.M.; Fedotov, M.E.

    1975-01-01

    A process is described for the production of an alloy consiting of 1 to 20% In, 0.5 to 15% Sm, and from 3 to 18% Hf, the balance being Ni. Such alloys show a good absorption capacity for thermal and intermediate neutrons, good neutron capture efficiency, and good corrosion resistance, and find application in nuclear reactor automatic control and safety systems. The Hf provides for the maintenance of a reasonably high order of neutron capture efficiency throughout the lifetime of a reactor. The alloys are formed in a vacuum furnace operating with an inert gas atmosphere at 280 to 300 mm.Hg. They have a corrosion resistance from 3 to 3.5 times that of the Ag-based alloys commonly employed, and a neutron capture efficiency about twice that of the Ag alloys. Castability and structural strength are good. (U.K.)

  5. Studsvik thermal neutron facility

    International Nuclear Information System (INIS)

    Pettersson, O.A.; Larsson, B.; Grusell, E.; Svensson, P.

    1992-01-01

    The Studsvik thermal neutron facility at the R2-0 reactor originally designed for neutron capture radiography has been modified to permit irradiation of living cells and animals. A hole was drilled in the concrete shielding to provide a cylindrical channel with diameter of 25.3 cm. A shielding water tank serves as an entry holder for cells and animals. The advantage of this modification is that cells and animals can be irradiated at a constant thermal neutron fluence rate of approximately 10 9 n cm -2 s -1 (at 100 kW) without stopping and restarting the reactor. Topographic analysis of boron done by neutron capture autoradiography (NCR) can be irradiated under the same conditions as previously

  6. The intense neutron generator

    International Nuclear Information System (INIS)

    Lewis, W.B.

    1966-01-01

    The presentation discusses both the economic and research contexts that would be served by producing neutrons in gram quantities at high intensities by electrical means without uranium-235. The revenue from producing radioisotopes is attractive. The array of techniques introduced by the multipurpose 65 megawatt Intense Neutron Generator project includes liquid metal cooling, superconducting magnets for beam bending and focussing, super-conductors for low-loss high-power radiofrequency systems, efficient devices for producing radiofrequency power, plasma physics developments for producing and accelerating hydrogen, ions at high intensity that are still far out from established practice, a multimegawatt high voltage D.C. generating machine that could have several applications. The research fields served relate principally to materials science through neutron-phonon and other quantum interactions as well as through neutron diffraction. Nuclear physics is served through μ-, π- and K-meson production. Isotope production enters many fields of applied research. (author)

  7. Neutrons and fusion

    International Nuclear Information System (INIS)

    Maynard, C.W.

    1976-01-01

    The production of energy from fusion reactions does not require neutrons in the fundamental sense that they are required in a fission reactor. Nevertheless, the dominant fusion reaction, that between deuterium and tritium, yields a 14 MeV neutron. To contrast a fusion reactor based on this reaction with the fission case, 3 x 10 20 such neutrons produced per gigawatt of power. This is four times as many neutrons as in an equivalent fission reactor and they carry seven times the energy of the fission neutrons. Thus, they dominate the energy recovery problem and create technological problems comparable to the original plasma confinement problem as far as a practical power producing device is concerned. Further contrasts of the fusion and fission cases are presented to establish the general role of neutrons in fusion devices. Details of the energy deposition processes are discussed and those reactions necessary for producing additional tritium are outlined. The relatively high energy flux with its large intensity will activate almost any materials of which the reactor may be composed. This activation is examined from the point of view of decay heat, radiological safety, and long-term storage. In addition, a discussion of the deleterious effects of neutron interactions on materials is given in some detail; this includes the helium and hydrogen producing reactions and displacement rate of the lattice atoms. The various materials that have been proposed for structural purposes, for breeding, reflecting, and moderating neutrons, and for radiation shielding are reviewed from the nuclear standpoint. The specific reactions of interest are taken up for various materials and finally a report is given on the status and prospects of data for fusion studies

  8. Scope of neutron interferometry

    International Nuclear Information System (INIS)

    Rauch, H.

    1978-01-01

    This paper deals with the interferometry of well separated coherent beams, where the phase of the beams can be manipulated individually. The basic equation of the dynamical neutron diffraction theory are recalled. The various contributions to the interaction of as low neutron with its surroundings are discussed: the various terms denote the nuclear, magnetic, electromagnetic, intrinsic, gravitational, and weak interaction respectively. Applications to nuclear physics, fundamental physics and solid state physics are successively envisaged

  9. Pulsed spallation Neutron Sources

    International Nuclear Information System (INIS)

    Carpenter, J.M.

    1994-01-01

    This paper reviews the early history of pulsed spallation neutron source development at Argonne and provides an overview of existing sources world wide. A number of proposals for machines more powerful than currently exist are under development, which are briefly described. The author reviews the status of the Intense Pulsed Neutron Source, its instrumentation, and its user program, and provides a few examples of applications in fundamental condensed matter physics, materials science and technology

  10. Pulsed spallation neutron sources

    International Nuclear Information System (INIS)

    Carpenter, J.M.

    1996-01-01

    This paper reviews the early history of pulsed spallation neutron source development ar Argonne and provides an overview of existing sources world wide. A number of proposals for machines more powerful than currently exist are under development, which are briefly described. The author reviews the status of the Intense Pulsed Neutron Source, its instrumentation, and its user program, and provide a few examples of applications in fundamental condensed matter physics, materials science and technology

  11. Introduction to neutron scattering

    Energy Technology Data Exchange (ETDEWEB)

    Fischer, W E [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1996-11-01

    We give here an introduction to the theoretical principles of neutron scattering. The relationship between scattering- and correlation-functions is particularly emphasized. Within the framework of linear response theory (justified by the weakness of the basic interaction) the relation between fluctuation and dissipation is discussed. This general framework explains the particular power of neutron scattering as an experimental method. (author) 4 figs., 4 refs.

  12. Electron volt neutron spectrometers

    International Nuclear Information System (INIS)

    Pietropaolo, A.; Senesi, R.

    2011-01-01

    The advent of pulsed neutron sources has made available intense fluxes of epithermal neutrons (500 meV ≤E≤100 eV ). The possibility to open new investigations on condensed matter with eV neutron scattering techniques, is related to the development of methods, concepts and devices that drive, or are inspired by, emerging studies at this energy scale. Electron volt spectrometers have undergone continuous improvements since the construction of the first prototype instruments, but in the last decade major breakthroughs have been accomplished in terms of resolution and counting statistics, leading, for example, to the direct measurement of the proton 3-D Born–Oppenheimer potential in any material, or to quantitatively probe nuclear quantum effects in hydrogen bonded systems. This paper reports on the most effective methods and concepts for energy analysis and detection, as well as devices for the optimization of electron volt spectrometers for different applications. This is set in the context of the progress made up to date in instrument development. Starting from early stages of development of the technique, particular emphasis will be given to the Vesuvio eV spectrometer at the ISIS neutron source, the first spectrometer where extensive scientific, as well as research and development programmes have been carried out. The potential offered by this type of instrumentation, from single particle excitations to momentum distribution studies, is then put in perspective into the emerging fields of eV spectroscopy applied to cultural heritages and neutron irradiation effects in electronics. - Highlights: ► Neutron spectrometers at eV energies. ► Methods and techniques for eV neutrons counting at spallation sources. ► Scattering, imaging and radiation hardness tests with multi-eV neutrons.

  13. Neutron electromagnetic form factors

    International Nuclear Information System (INIS)

    Finn, J.M.; Madey, R.; Eden, T.; Markowitz, P.; Rutt, P.M.; Beard, K.; Anderson, B.D.; Baldwin, A.R.; Keane, D.; Manley, D.M.; Watson, J.W.; Zhang, W.M.; Kowalski, S.; Bertozzi, W.; Dodson, G.; Farkhondeh, M.; Dow, K.; Korsch, W.; Tieger, D.; Turchinetz, W.; Weinstein, L.; Gross, F.; Mougey, J.; Ulmer, P.; Whitney, R.; Reichelt, T.; Chang, C.C.; Kelly, J.J.; Payerle, T.; Cameron, J.; Ni, B.; Spraker, M.; Barkhuff, D.; Lourie, R.; Verst, S.V.; Hyde-Wright, C.; Jiang, W.-D.; Flanders, B.; Pella, P.; Arenhoevel, H.

    1992-01-01

    Nucleon form factors provide fundamental input for nuclear structure and quark models. Current knowledge of neutron form factors, particularly the electric form factor of the neutron, is insufficient to meet these needs. Developments of high-duty-factor accelerators and polarization-transfer techniques permit new experiments that promise results with small sensitivities to nuclear models. We review the current status of the field, our own work at the MIT/Bates linear accelerator, and future experimental efforts

  14. Neutron ion temperature measurement

    International Nuclear Information System (INIS)

    Strachan, J.D.; Hendel, H.W.; Lovberg, J.; Nieschmidt, E.B.

    1986-11-01

    One important use of fusion product diagnostics is in the determination of the deuterium ion temperature from the magnitude of the 2.5 MeV d(d,n) 3 He neutron emission. The detectors, calibration methods, and limitations of this technique are reviewed here with emphasis on procedures used at PPPL. In most tokamaks, the ion temperature deduced from neutrons is in reasonable agreement with the ion temperature deduced by other techniques

  15. Nuclear polarization and neutrons

    International Nuclear Information System (INIS)

    Glaettli, H.

    1985-01-01

    Different possibilities for the use of polarized nuclei in thermal neutron scattering on condensed matter are reviewed. Highly polarized nuclei are the starting point for studying dipolar magnetic order. Systematic measurement of spin-dependent scattering lengths is possible on samples with polarized nuclei. Highly polarized hydrogen should help to unravel complicated structures in chemistry and biology. The use of polarized proton targets as an energy-independent neutron polarizer in the thermal and epithermal region should be considered afresh. (author)

  16. Forensic neutron activation analysis

    International Nuclear Information System (INIS)

    Kishi, T.

    1987-01-01

    The progress of forensic neutron activation analysis (FNAA) in Japan is described. FNAA began in 1965 and during the past 20 years many cases have been handled; these include determination of toxic materials, comparison examination of physical evidences (e.g., paints, metal fragments, plastics and inks) and drug sample differentiation. Neutron activation analysis is applied routinely to the scientific criminal investigation as one of multielement analytical techniques. This paper also discusses these routine works. (author) 14 refs

  17. Quantum physics with neutrons

    International Nuclear Information System (INIS)

    Durstberger, K.; Hasegawa, Y.; Klepp, J.; Sulyok, G.; Rauch, H.

    2008-01-01

    Full text: Fundamental quantum properties like quantum coherence and entanglement are among the most interesting features of quantum mechanics. The physical system of interest is the (massive) neutron subjected to interferometric and polarimetric measurements. Neutrons are proper objects for a study of quantum mechanical behavior: they allow for rather easy experimental control and the neutron spin is the simplest two-level system with easy manipulation by magnetic fields. In combination with interferometric measurements the system has enough intrinsic richness to show interesting quantum features such as entanglement. The coupling of the neutron to an external magnetic field allows for selective manipulations of the spinor quantum states. This can be used, on the one hand, to create entangled states where the entanglement occurs between different degrees of freedom (e.g. spin and path) and, on the other hand, one can introduce dephasing and decoherence by varying magnetic fields. We investigate different kinds of entanglement for the neutron system and mechanisms for decoherence and dephasing. We discuss weak measurements and their realization for neutrons where information about the system can be revealed without disturbing the system too much. Beyond the theoretical work we develop experimental strategies to check the results directly in suitably designed experiments. The experimental work is done at the Institute Laue-Langvine (ILL) in Grenoble, France. (author)

  18. Neutron scattering in Australia

    International Nuclear Information System (INIS)

    Knott, R.B.

    1994-01-01

    Neutron scattering techniques have been part of the Australian scientific research community for the past three decades. The High Flux Australian Reactor (HIFAR) is a multi-use facility of modest performance that provides the only neutron source in the country suitable for neutron scattering. The limitations of HIFAR have been recognized and recently a Government initiated inquiry sought to evaluate the future needs of a neutron source. In essence, the inquiry suggested that a delay of several years would enable a number of key issues to be resolved, and therefore a more appropriate decision made. In the meantime, use of the present source is being optimized, and where necessary research is being undertaken at major overseas neutron facilities either on a formal or informal basis. Australia has, at present, a formal agreement with the Rutherford Appleton Laboratory (UK) for access to the spallation source ISIS. Various aspects of neutron scattering have been implemented on HIFAR, including investigations of the structure of biological relevant molecules. One aspect of these investigations will be presented. Preliminary results from a study of the interaction of the immunosuppressant drug, cyclosporin-A, with reconstituted membranes suggest that the hydrophobic drug interdigitated with lipid chains

  19. Neutron scattering in Australia

    Energy Technology Data Exchange (ETDEWEB)

    Knott, R.B. [Australian Nuclear Science and Technology Organisation, Menai (Australia)

    1994-12-31

    Neutron scattering techniques have been part of the Australian scientific research community for the past three decades. The High Flux Australian Reactor (HIFAR) is a multi-use facility of modest performance that provides the only neutron source in the country suitable for neutron scattering. The limitations of HIFAR have been recognized and recently a Government initiated inquiry sought to evaluate the future needs of a neutron source. In essence, the inquiry suggested that a delay of several years would enable a number of key issues to be resolved, and therefore a more appropriate decision made. In the meantime, use of the present source is being optimized, and where necessary research is being undertaken at major overseas neutron facilities either on a formal or informal basis. Australia has, at present, a formal agreement with the Rutherford Appleton Laboratory (UK) for access to the spallation source ISIS. Various aspects of neutron scattering have been implemented on HIFAR, including investigations of the structure of biological relevant molecules. One aspect of these investigations will be presented. Preliminary results from a study of the interaction of the immunosuppressant drug, cyclosporin-A, with reconstituted membranes suggest that the hydrophobic drug interdigitated with lipid chains.

  20. LHD neutron diagnostics

    International Nuclear Information System (INIS)

    Isobe, M.; Ogawa, K.; Kobuchi, T.

    2015-01-01

    The Large Helical Device (LHD) project will step into a next stage, i.e. experiment by using deuterium gases after two years of preparation. A comprehensive set of neutron and γ-ray diagnostics is going to be installed on the LHD towards extension of energetic-particle (EP) physics research in heliotron plasmas. Conceptual design of fusion products diagnostics for the LHD was made in late 1990s. After conclusion of agreements for the LHD deuterium experiment with local government bodies, development of FPs diagnostics has begun lately. Because there are a lot of tasks to do, all Japan fusion neutron and γ-ray diagnostics team has been organized in the collaboration framework of National Institute for Fusion Science. FPs diagnostics system on the LHD will consist of 1) wide dynamic range neutron flux monitor (NFM), 2) neutron activation system (NAS), 3) vertical neutron camera (VNC). In addition to these, we are developing a directional scintillating fiber detector, an artificial diamond detector and a γ-ray scintillation detector for confinement study of MeV ions. A neutron energy spectrometer prototype is also being developed and tested in KSTAR. In this paper, roles of NFM, NAS and VNC and current status of implementation onto the LHD are briefly described. (author)

  1. Neutrons for materials science

    International Nuclear Information System (INIS)

    Windsor, C.G.; Allen, A.J.; Hutchings, M.T.; Sayers, C.M.; Sinclair, R.N.; Schofield, P.; Wright, C.J.

    1984-12-01

    The discussion will be limited to applied materials research performed on a customer/contractor basis. The information obtained using neutrons must therefore compete both scientifically and financially with information obtained using other techniques, particularly electron microscopy, X-ray, NMR, infra-red and Raman spectroscopy. It will be argued that the unique nature of the information gained from neutrons often outweighs the undoubted difficulties of access to neutron beams. Examples are given. Small angle scattering has emerged as the neutron technique of widest application in applied materials research. The penetration of neutron beams through containment vessels, as well as through the sample, allows the measurement of 'in situ' time dependent experiments within a furnace, cryostat, pressure vessel or chemical reactor vessel. High resolution powder diffraction is another technique with wide applications. Structural studies are possible on increasing complex phases. The structure and volume fraction of minority phases can be measured at levels appreciably below that possible by X-ray diffraction. A rapidly growing field at present is the measurement of internal strains through the small shifts in lattice spacing. Inelastic scattering measurements exploit the unique property of neutrons to measure the orientations of vibrating molecules. (author)

  2. Neutron imaging plates

    International Nuclear Information System (INIS)

    Niimura, Nobuo

    1995-01-01

    Imaging plates have been used in the field of medical diagnosis since long ago, but their usefulness was verified as the two-dimensional detector for analyzing the X-ray crystalline structure of high bio molecules like protein, and they have contributed to the remarkable progress in this field. The great contribution is due to the excellent features, such as the detection efficiency of about 100%, the positional resolution smaller than 0.2 mm, the dynamic range of five digits, and the area of several hundreds mm square. The neutron imaging plates have not yet obtained the sufficient results. It was planned to construct the neutron diffractometer for biological matters, and to put imaging plate neutron detectors (IP-ND) to practical use as the detector. The research on the development of IP-NDs was carried out, and the IPp-NDs having the performance comparable with that for X-ray were able to be produced. Imaging plates are the integral type two-dimensional radiation detector using photostimulated luminescence matters, and their principle is explained. As to neutron imaging plates, the converter, neutron detection efficiency and the flight of secondary particles in photo-stimulated luminescence matters are described. As for the present state of development of neutron imaging plates, the IP-NDs made for trial, the dynamic range, the positional resolution, the detection efficiency and the kinds of converters, and the application of IP-NDs are reported. (K.I.)

  3. Neutron flux monitoring device

    International Nuclear Information System (INIS)

    Shimazu, Yoichiro.

    1995-01-01

    In a neutron flux monitoring device, there are disposed a neutron flux measuring means for outputting signals in accordance with the intensity of neutron fluxes, a calculation means for calculating a self power density spectrum at a frequency band suitable to an object to be measured based on the output of the neutron flux measuring means, an alarm set value generation means for outputting an alarm set value as a comparative reference, and an alarm judging means for comparing the alarm set value with the outputted value of the calculation means to judge requirement of generating an alarm and generate an alarm in accordance with the result of the judgement. Namely, the time-series of neutron flux signals is put to fourier transformation for a predetermined period of time by the calculation means, and from each of square sums for real number component and imaginary number component for each of the frequencies, a self power density spectrum in the frequency band suitable to the object to be measured is calculated. Then, when the set reference value is exceeded, an alarm is generated. This can reliably prevent generation of erroneous alarm due to neutron flux noises and can accurately generate an alarm at an appropriate time. (N.H.)

  4. Neutron Diffractometer; Neutronski difraktometar

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-12-15

    RA nuclear reactor is considered as a relatively strong neutron source producing the thermal neutron flux of about 3x10{sup 13} n/cm{sup 2} sec when operating at nominal power of 6.5 MW. Neutron diffraction method is applied in the field of solid state physics, material science, crystallography, magnetism, nuclear physic. Neutron diffractometer at the RA reactor consists of: system for obtaining collimated neutron beam from the horizontal experimental channel neutron monochromator; goniometer and electronic equipment for measurements and collecting the the measurement data. Nuklearni reaktor RA koji pri radu na snazi od 6,5 MW ima fluks termalnih neutrona oko 3x10{sup 13} n/cm{sup 2} sec predstavlja relativno jak izvor neutrona. Tehnika difrakcije neutrona primenjuje se u istrazivanjima fizike crvstog stanja, strukture materijala, kristalografije, magnetizma, nuklearne fizike. Neutronski difraktometar na reaktoru RA sastoji se od sistema za dobijanje kolimisanog snopa neutrona kroz horizontalni kanal reaktora; neutroskog monohromatora; goniometra i elektronskih uredjaja za merenja i registrovanje rezultata. Ovaj izvestaj sadrzi detaljan opis i seme neutronskog difraktometra sa pratecom opremom i elektronskim komponentama.

  5. Neutron measuring device

    International Nuclear Information System (INIS)

    Hatayama, Akiyoshi; Seki, Eiji; Kita, Yoshio; Nishitani, Takeo.

    1993-01-01

    The device of the present invention concerns measurement for neutrons in a tokamak type thermonuclear device and it can measure total amount of generated neutrons accurately throughout the operation period even if an error is caused in counted values by plasma disruption. That is, the device comprises (1) a means for detecting presence or absence of occurrence of plasma disruption and the time for the initiation of the occurrence, (2) a first data processing means for processing detection signals, (3) a means for detecting neutrons generated in plasmas and (4) a second data processing means for calculating integrated values for the number of neutrons generated from the start to the completion of electric discharge when no disruption occurs and calculating integrated values for the number of generated neutrons from the start of electric discharge to the time at the initiation of occurrence of the disruption when disruption is present. In the thus constituted device, even if an error is caused by frequent occurrence of plasma disruption, total time integrated amount of neutrons generated in the plasmas can be measured accurately. (I.S.)

  6. Neutron beam applications

    International Nuclear Information System (INIS)

    Lee, Chang Hee; Lee, J. S.; Seong, B. S.

    2000-05-01

    For the materials science by neutron technique, the development of the various complementary neutron beam facilities at horizontal beam port of HANARO and the techniques for measurement and analysis has been performed. High resolution powder diffractometer, after the installation and performance test, has been opened and used actively for crystal structure analysis, magnetic structure analysis, phase transition study, etc., since January 1998. The main components for four circle diffractometer were developed and, after performance test, it has been opened for crystal structure analysis and texture measurement since the end of 1999. For the small angle neutron spectrometer, the main component development and test, beam characterization, and the preliminary experiment for the structure study of polymer have been carried out. Neutron radiography facility, after the precise performance test, has been used for the non-destructive test of industrial component. Addition to the development of main instruments, for the effective utilization of those facilities, the scattering techniques relating to quantitative phase analysis, magnetic structure analysis, texture measurement, residual stress measurement, polymer study, etc, were developed. For the neutron radiography, photographing and printing technique on direct and indirect method was stabilized and the development for the real time image processing technique by neutron TV was carried out. The sample environment facilities for low and high temperature, magnetic field were also developed

  7. Application of neutron activation techniques and x-ray energy dispersion spectrometry, in analysis of metallic traces adsorbed by chelex-100 resin; Ativacao das tecnicas de ativacao neutronica e espectrometria por dispersao de onda e de energia de raios X, na analise de tracos metalicos adsorvidos pela resina chelex-100

    Energy Technology Data Exchange (ETDEWEB)

    Fernandes, Jair C.; Amaral, Angela M.; Magalhaes, Jesus C.; Pereira, Jose S.J.; Silva, Juliana B. da; Auler, Lucia M.L.A. [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil)]. E-mail: jcf@urano.cdtn.br

    2000-07-01

    In this work, the authors have investigated optimal conditions of adsorption for several ion metallic groups (cations of heavy metals and transition metals, oxyanions metallics and metalloids and cations of rare earths), as traces (ppb), withdrawn and in mixture of groups, by chelex-100 resin. The experiments have been developed by bath techniques in ammonium acetate tamponade solution 40 mM pH 5,52 content 0,5 g of chelex-100 resin. After magnetic agitation for two hours, resins were dried and submitted to X-ray energy dispersion spectrometry, x-ray fluorescence spectrometry and neutron activation analysis. The results have demonstrated that chelex-100 resin adsorb quantitatively transition element groups and rare earth groups in two cases (withdrawn and simultaneously adsorption)

  8. Evaluation and standardization of neutron activation analysis according to the K{sub 0} method in the RP-10 reactor; Evaluacion y estandarizacion del analisis por activacion neutronica segun el metodo del K{sub 0} en el reactor nuclear RP-10

    Energy Technology Data Exchange (ETDEWEB)

    Montoya R, E

    1995-06-01

    It has been characterized and standardized an irradiation of the RP-10 Research Nuclear Reactor for use of the K{sub 0} method of neutron activation analysis using the Hoegdahl convention; also it has been evaluate the behaviour of such method in regard to the accuracy and precision of the results obtained in the quantitative multi elemental analysis of several certified materials of reference. In order to prove that the analytical method is totally under statistical control, it has been used the Heydorn method. It has been verified that the method is exact, precise and reliable to determine the aluminium, antimuonium, arsenic, bromine, calcium, chloride, copper, magnesium, manganese, sodium, titanium, vanadium, zinc and other elements. Also, they are discussed, in regard to the use of K{sub 0} constants, the different formalisms employed to calculate the integral of the reaction rate by nucleus in the activation. (author). 58 refs., 18 tabs., 6 figs.

  9. MAGNETIC NEUTRON SCATTERING

    Energy Technology Data Exchange (ETDEWEB)

    ZALIZNYAK,I.A.; LEE,S.H.

    2004-07-30

    Much of our understanding of the atomic-scale magnetic structure and the dynamical properties of solids and liquids was gained from neutron-scattering studies. Elastic and inelastic neutron spectroscopy provided physicists with an unprecedented, detailed access to spin structures, magnetic-excitation spectra, soft-modes and critical dynamics at magnetic-phase transitions, which is unrivaled by other experimental techniques. Because the neutron has no electric charge, it is an ideal weakly interacting and highly penetrating probe of matter's inner structure and dynamics. Unlike techniques using photon electric fields or charged particles (e.g., electrons, muons) that significantly modify the local electronic environment, neutron spectroscopy allows determination of a material's intrinsic, unperturbed physical properties. The method is not sensitive to extraneous charges, electric fields, and the imperfection of surface layers. Because the neutron is a highly penetrating and non-destructive probe, neutron spectroscopy can probe the microscopic properties of bulk materials (not just their surface layers) and study samples embedded in complex environments, such as cryostats, magnets, and pressure cells, which are essential for understanding the physical origins of magnetic phenomena. Neutron scattering is arguably the most powerful and versatile experimental tool for studying the microscopic properties of the magnetic materials. The magnitude of the cross-section of the neutron magnetic scattering is similar to the cross-section of nuclear scattering by short-range nuclear forces, and is large enough to provide measurable scattering by the ordered magnetic structures and electron spin fluctuations. In the half-a-century or so that has passed since neutron beams with sufficient intensity for scattering applications became available with the advent of the nuclear reactors, they have became indispensable tools for studying a variety of important areas of modern

  10. Neutron dosimetry in boron neutron capture therapy

    International Nuclear Information System (INIS)

    Fairchild, R.G.; Miola, U.J.; Ettinger, K.V.

    1981-01-01

    The recent development of various borated compounds and the utilization of one of these (Na 2 B 12 H 11 SH) to treat brain tumors in clinical studies in Japan has renewed interest in neutron capture therapy. In these procedures thermal neutrons interact with 10 B in boron containing cells through the 10 B(n,α) 7 Li reaction producing charged particles with a maximum range of approx. 10μm in tissue. Borated analogs of chlorpromazine, porphyrin, thiouracil and deoxyuridine promise improved tumor uptake and blood clearance. The therapy beam from the Medical Research Reactor in Brookhaven contains neutrons from a modified and filtered fission spectrum and dosimetric consequences of the use of the above mentioned compounds in conjunction with thermal and epithermal fluxes are discussed in the paper. One of the important problems of radiation dosimetry in capture therapy is determination of the flux profile and, hence, the dose profile in the brain. This has been achieved by constructing a brain phantom made of TE plastic. The lyoluminescence technique provides a convenient way of monitoring the neutron flux distributions; the detectors for this purpose utilize 6 Li and 10 B compounds. Such compounds have been synthesized specially for the purpose of dosimetry of thermal and epithermal beams. In addition, standard lyoluminescent phosphors, like glutamine, could be used to determine the collisional component of the dose as well as the contribution of the 14 N(n,p) 14 C reaction. Measurements of thermal flux were compared with calculations and with measurements done with activation foils

  11. Pulsed neutron generator for use with pulsed neutron activation techniques

    International Nuclear Information System (INIS)

    Rochau, G.E.

    1980-01-01

    A high-output, transportable, pulsed neutron generator has been developed by Sandia National Laboratories for use with Pulsed Neutron Activation (PNA) techniques. The PNA neutron generator generates > 10 10 14 MeV D-T neutrons in a 1.2 millisecond pulse. Each operation of the unit will produce a nominal total neutron output of 1.2 x 10 10 neutrons. The generator has been designed to be easily repaired and modified. The unit requires no additional equipment for operation or measurement of output

  12. Las cosas por su nombre

    OpenAIRE

    Storani, Emilia

    2017-01-01

    El artículo propone indagar sobre los modos y diferentes formatos que se utilizan tanto en la escritura como en la lectura, para articular con las luchas por la identidad de género. La Ley de Identidad de Género ha sido un puntapié clave para pensarnos a nosotros mismos culturalmente y para pensar a los demás. Pero, ¿cómo mencionamos, escribimos y leemos las diferentes identidades? La escritura, también es un mundo transformador para quienes bregan por una sociedad más libre y sin prejuicios....

  13. Ptose palpebral causada por Paquidermoperiostose

    Directory of Open Access Journals (Sweden)

    Patricia Regina de Pinho Tavares

    2014-08-01

    Full Text Available A paquidermoperiostose é uma síndrome caracterizada por acometimento cutâneo e ósseo, e em alguns casos ocorre comprometimento palpebral leve. É uma síndrome rara, idiopática ou hereditária, com provável herança autossômica dominante de penetrância variável. Descreve-se o caso de um paciente com ptose grave por paquidermoperiostose elucidando sua fisiopatologia e conduta cirúrgica aplicada.

  14. Diverticulitis yeyunal perforada por enterolito.

    OpenAIRE

    Marenco De la Cuadra, Beatriz; Gomez-Rosado, Juan-Carlos; Capitan-Morales, Luis-Cristobal; Valdés Hernández, Javier; Reyes-lopera, N.J. De los

    2012-01-01

    La diverticulosis yeyunal es una enfermedad adquirida rara. Casi el 60-70% keeps asymptomátic or Con síntomas crónicos inespecíficos, aunque puede presentarse como un abdomen agudo. La perforación debida a enterolitos es una causa extremadamente rara do complicación, y puede producirse por la impactación de ésta contra la pared intestinal. Presentamos caso de un varón de 82 años que acude a urgencias por un dolor súbito abdominal, difuso, con irritación peritoneal, leucocitosis con neutro...

  15. Mortalidad intrahospitalaria por accidente cerebrovascular

    OpenAIRE

    Federico Rodríguez Lucci; Virginia Pujol Lereis; Sebastián Ameriso; Guillermo Povedano; María F. Díaz; Alejandro Hlavnicka; Néstor A. Wainsztein; Sebastián F. Ameriso

    2013-01-01

    La mortalidad global por accidente cerebrovascular (ACV) ha disminuido en las últimas tres décadas, probablemente debido a un mejor control de los factores de riesgo vascular. La mortalidad hospitalaria por ACV ha sido tradicionalmente estimada entre 6 y 14% en la mayoría de las series comunicadas. Sin embargo, los datos de ensayos clínicos recientes sugieren que esta cifra sería sustancialmente menor. Se revisaron datos de pacientes internados con diagnóstico de ACV del Banco de Datos de Str...

  16. Radiography with polarised neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Schulz, Michael L.

    2010-08-20

    In this thesis I present a new technique for the spatially resolved investigation of the magnetic properties of bulk samples. Standard one dimensional neutron depolarisation analysis is combined with neutron radiography to a method we call Neutron Depolarisation Imaging (NDI). The experimental setup which was installed at the neutron radiography beam line ANTARES at FRM II consists of a double crystal monochromator, neutron polariser, spin flipper, polarisation analyser and a position sensitive CCD detector. A comprehensive discussion of the requirements for these components is given and the limitations of the method are shown. The maximum spatial resolution which can be achieved with a neutron radiography setup is determined by the collimation of the neutron beam and the distance between sample and detector. Different types of polarisers have been tested and their advantages and disadvantages are discussed. A double crystal monochromator and a new type of polariser employing polarising neutron supermirrors based on the principle of an optical periscope were developed and tested during this work. Furthermore, NDI measurements on various samples of the weakly ferromagnetic materials Pd{sub 1-x}Ni{sub x} and Ni{sub 3}Al are presented. Neutron depolarisation radiography and tomography measurements were conducted with a spatial resolution as high as 0.3 mm on Pd{sub 1-x}Ni{sub x} and Ni{sub 3}Al samples. The feasibility of NDI experiments under hydrostatic pressures up to 10 kbar was shown on a sample of Ni{sub 3}Al using a modified Cu:Be clamp cell. A decrease of the ordering temperature by 2 K under hydrostatic pressure was determined from the NDI measurements and shows the potential of the method for further high pressure experiments. Additionally a method was developed which in principle allows to obtain the intrinsic dependence of the ordering temperature T{sub C} on the ordered moment Ms from NDI measurements on inhomogeneous samples containing regions with

  17. Radiography with polarised neutrons

    International Nuclear Information System (INIS)

    Schulz, Michael L.

    2010-01-01

    In this thesis I present a new technique for the spatially resolved investigation of the magnetic properties of bulk samples. Standard one dimensional neutron depolarisation analysis is combined with neutron radiography to a method we call Neutron Depolarisation Imaging (NDI). The experimental setup which was installed at the neutron radiography beam line ANTARES at FRM II consists of a double crystal monochromator, neutron polariser, spin flipper, polarisation analyser and a position sensitive CCD detector. A comprehensive discussion of the requirements for these components is given and the limitations of the method are shown. The maximum spatial resolution which can be achieved with a neutron radiography setup is determined by the collimation of the neutron beam and the distance between sample and detector. Different types of polarisers have been tested and their advantages and disadvantages are discussed. A double crystal monochromator and a new type of polariser employing polarising neutron supermirrors based on the principle of an optical periscope were developed and tested during this work. Furthermore, NDI measurements on various samples of the weakly ferromagnetic materials Pd 1-x Ni x and Ni 3 Al are presented. Neutron depolarisation radiography and tomography measurements were conducted with a spatial resolution as high as 0.3 mm on Pd 1-x Ni x and Ni 3 Al samples. The feasibility of NDI experiments under hydrostatic pressures up to 10 kbar was shown on a sample of Ni 3 Al using a modified Cu:Be clamp cell. A decrease of the ordering temperature by 2 K under hydrostatic pressure was determined from the NDI measurements and shows the potential of the method for further high pressure experiments. Additionally a method was developed which in principle allows to obtain the intrinsic dependence of the ordering temperature T C on the ordered moment Ms from NDI measurements on inhomogeneous samples containing regions with different ordering temperatures. This

  18. The secondary neutron sources for generation of particular neutron fluxes

    International Nuclear Information System (INIS)

    Tracz, G.

    2007-07-01

    The foregoing paper presents the doctor's thesis entitled '' The secondary neutron sources for generation of particular neutron fluxes ''. Two secondary neutron sources have been designed, which exploit already existing primary sources emitting neutrons of energies different from the desired ones. The first source is devoted to boron-neutron capture therapy (BNCT). The research reactor MARIA at the Institute of Atomic Energy in Swierk (Poland) is the primary source of the reactor thermal neutrons, while the secondary source should supply epithermal neutrons. The other secondary source is the pulsed source of thermal neutrons that uses fast 14 MeV neutrons from a pulsed generator at the Institute of Nuclear Physics PAN in Krakow (Poland). The physical problems to be solved in the two mentioned cases are different. Namely, in order to devise the BNCT source the initial energy of particles ought to be increased, whilst in the other case the fast neutrons have to be moderated. Slowing down of neutrons is relatively easy since these particles lose energy when they scatter in media; the most effective moderators are the materials which contain light elements (mostly hydrogen). In order to increase the energy of neutrons from thermal to epithermal (the BNCT case) the so-called neutron converter should be exploited. It contains a fissile material, 235 U. The thermal neutrons from the reactor cause fission of uranium and fast neutrons are emitted from the converter. Then fissile neutrons of energy of a few MeV are slowed down to the required epithermal energy range. The design of both secondary sources have been conducted by means of Monte Carlo simulations, which have been carried out using the MCNP code. In the case of the secondary pulsed thermal neutron source, some of the calculated results have been verified experimentally. (author)

  19. 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

    Energy Technology Data Exchange (ETDEWEB)

    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

  20. Semiconductor Thermal Neutron Detector

    Directory of Open Access Journals (Sweden)

    Toru Aoki

    2014-02-01

    Full Text Available The  CdTe  and  GaN  detector  with  a  Gd  converter  have  been developed  and  investigated  as  a  neutron  detector  for neutron  imaging.  The  fabricated  Gd/CdTe  detector  with  the  25  mm  thick  Gd  was  designed  on  the  basis  of  simulation results  of  thermal  neutron  detection  efficiency  and  spatial  resolution.  The  Gd/CdTe  detector  shows  the  detection  of neutron  capture  gamma  ray  emission  in  the  155Gd(n,  g156Gd,  157Gd(n,  g158Gd  and  113Cd(n,  g114Cd  reactions  and characteristic X-ray emissions due to conversion-electrons generated inside the Gd film. The observed efficient thermal neutron detection with the Gd/CdTe detector shows its promise in neutron radiography application. Moreover, a BGaN detector has also investigated to separate neutron signal from gamma-ray clearly. 

  1. Neutrons for materials science

    International Nuclear Information System (INIS)

    Windsor, C.G.; Allen, A.J.; Hutchings, M.T.; Sayers, C.M.; Sinclair, R.N.; Schofield, P.; Wright, C.J.

    1985-01-01

    The discussion will be limited to applied materials research performed on a customer/contractor basis. The information obtained using neutrons must therefore compete both scientifically and financially with information obtained using other techniques, particular electron microscopy, X-ray, NMR, infra-red and Raman spectroscopy. It will be argued that the unique nature of the information gained from neutrons often outweighs the undoubted difficulties of access to neutron beams. Small-angle scattering has emerged as the neutron technique of widest application in applied materials research. The penetration of neutron beams through containment vessels, as well as through the sample, allows the measurement of in situ time-dependent experiments within a furnace, cryostat, pressure vessel or chemical reactor vessel. Examples will be given of small-angle scattering projects from the nuclear metallurgy, coal, oil, cement, detergent and plastics industries. High-resolution powder diffraction is another technique with wide applications. Structural studies are possible on increasingly complex phases. The structure and volume fraction of minority phase can be measured at levels appreciably below that possible by X-ray diffraction. A rapidly growing field at present is the measurement of internal strains through the small shifts in lattice spacing. Neutron diffraction is unique in being able to measure the full strain tensor from a specified volume within a bulk specimen. Inelastic scattering measurements exploit the unique property of neutrons to measure the orientations of vibrating molecules. Examples will be chosen from the field of catalysis where inelastic spectroscopy has revealed the nature of the bonding of hydrocarbon molecules. (author)

  2. Neutron activation studies on JET

    International Nuclear Information System (INIS)

    Loughlin, M.J.; Forrest, R.A.; Edwards, J.E.G.

    2001-01-01

    Extensive neutron transport calculations have been performed to determine the neutron spectrum at a number of points throughout the JET torus hall. The model has been bench-marked against a set of foil activation measurements which were activated during an experimental campaign with deuterium/tritium plasmas. The model can predict the neutron activation of the foils on the torus hall walls to within a factor of three for reactions with little sensitivity to thermal neutrons. The use of scandium foils with and without a cadmium thermal neutron absorber was a useful monitor of the thermal neutron flux. Conclusions regarding the usefulness of other foils for benchmarking the calculations are also given

  3. Neutron radiography, techniques and applications

    International Nuclear Information System (INIS)

    Domanus, J.C.

    1987-10-01

    After describing the principles of the ''in pool'' and ''dry'' installations, techniques used in neutron radiography are reviewed. Use of converter foils with silver halide films for the direct and transfer methods is described. Advantages of the use of nitrocellulose film for radiographying radioactive objects are discussed. Dynamic imaging is shortly reviewed. Standardization in the field of neutron radiography (ASTM and Euratom Neutron Radiography Working Group) is described. The paper reviews main fields of use of neutron radiography. Possibilities of use of neutron radiography at research reactors in various scientific, industrial and other fields are mentioned. Examples are given of application of neutron radiography in industry and the nuclear field. (author)

  4. Support for cold neutron utilization

    International Nuclear Information System (INIS)

    Lee, Kye Hong; Han, Young Soo; Choi, Sungmin; Choi, Yong; Kwon, Hoon; Lee, Kwang Hee

    2012-06-01

    - Support for experiments by users of cold neutron scattering instrument - Short-term training of current and potential users of cold neutron scattering instrument for their effective use of the instrument - International collaboration for advanced utilization of cold neutron scattering instruments - Selection and training of qualified instrument scientists for vigorous research endeavors and outstanding achievements in experiments with cold neutron - Research on nano/bio materials using cold neutron scattering instruments - Bulk nano structure measurement using small angle neutron scattering and development of analysis technique

  5. DESAJUSTE EDUCATIVO POR REGIONES EN COLOMBIA: ¿COMPETENCIA POR SALARIOS O POR PUESTOS DE TRABAJO?

    Directory of Open Access Journals (Sweden)

    Maribel Castillo Caicedo

    2007-06-01

    Full Text Available Este trabajo aporta una perspectiva del fenómeno de la sobreeducación, entendida como un desajuste por exceso, entre el nivel educativo alcanzado por el individuo y el exigido por el puesto de trabajo en el cual se desempeña; esto se debe a que existe una demanda laboral estrecha de puestos de trabajo para personas calificadas en Colombia. Se analizan las contribuciones empíricas existentes y el debate sobre las mismas; se examinan las teorías que permiten explicar la existencia de un desajuste educativo y se realiza una revisión de la literatura internacional y nacional sobre el tema. Adicionalmente, se plantean una serie de hipótesis para desarrollar un esquema que permita determinar el comportamiento del individuo en el fenómeno de la sobreeducación.

  6. Consanguinidad por isonimia en Salta

    Directory of Open Access Journals (Sweden)

    Albeza, María V.

    2007-01-01

    Full Text Available Se estimó el coeficiente de parentesco por isonimia para localidades de la Puna, Valle Calchaquí y Valle de Lerma, a fin de evaluar diferentes factores evolutivos que podrían estar afectando la composición genética de la población. A partir de los apellidos de las parejas consignadas en fuentes primarias de información, se estimó la isonimia conyugal o marital, el coeficiente total Ft y sus componentes Fr (inbreeding azaroso y Fn (inbreeding no azaroso. De las localidades estudiadas, en la Puna se ha detectado sólo una pareja isónima en una de ellas, en el Valle Calchaquí, tres y ninguna en el Valle de Lerma. Tanto en el Valle Calchaquí como en el de Lerma, se han estimado valores negativos de Ft, y en la Puna se registran los valores más elevados. En las localidades estudiadas no se cumple el supuesto de transmisión patrilineal de apellidos por lo que los valores de Fr y por ende de Ft podrían estar subestimados. Es por ello que sería necesario contar con información desde otras vertientes metodológicas para corroborar, complementar y manejar cuidadosamente el análisis de los datos y las conclusiones que se obtienen.

  7. Neutron-Induced Failures in Semiconductor Devices

    Energy Technology Data Exchange (ETDEWEB)

    Wender, Stephen Arthur [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-04-06

    This slide presentation explores single event effect, environmental neutron flux, system response, the Los Alamos Neutron Science Center (LANSCE) neutron testing facility, examples of SEE measurements, and recent interest in thermal neutrons.

  8. Celulitis por citomegalovirus Cytomegalovirus cellulitis

    Directory of Open Access Journals (Sweden)

    A. Ruiz Lascano

    2002-12-01

    Full Text Available Las lesiones cutáneas por citomegalovirus (CMV son infrecuentes y a menudo una manifestación tardía de una enfermedad sistémica, que generalmente anuncia un curso fatal. Comunicamos un caso de celulitis por CMV: una mujer de 70 años con trasplante renal efectuado 1 mes antes de la consulta, terapia inmunosupresora con ciclosporina A y metilprednisona. La paciente ingresó por fiebre, dolor e impotencia funcional en pierna derecha. Comprobamos la existencia de una placa de 8 por 4 cm eritematoedematosa. La tratamos con antibióticos sin mejoría, por lo que realizamos un estudio histopatológico de piel que mostró cambios citopáticos compatibles con infección por CMV. Los cultivos bacteriológicos y micológicos fueron negativos. La inmunohistoquímica específica para CMV y el estudio de reacción en cadena de la polimerasa (PCR de la biopsia de piel fueron positivas, al igual que la antigenemia. El tratamiento con ganciclovir produjo la mejoría del cuadro clínico. En la literatura revisada no hemos encontrado la celulitis como manifestación de enfermedad cutánea por CMV.Cutaneous lesions in CMV infection are rare, often a late manifestation of systemic infection, and usually herald a fatal course. A 70 year-old woman received a kidney transplantation one month before consulting and immunosuppressive therapy that included cyclosporine A and methylprednisone. She complained of fever, local pain in her right leg, and an erythematous and swelling plaque. She was treated with intravenous antibiotics without improvement. A skin biopsy was performed and the tissue obtained was sent for bacterial and fungal cultures as well as for histological examination. Cultures were negative. The biopsy showed CMV cytopathic changes. Immunoperoxidase staining was positive for CMV and polymerase chain reaction (PCR testing revealed CMV DNA. She was treated with ganciclovir with resolution of the lesion. CMV cellulitis is a rare cutaneous manifestation

  9. Development of highly effective neutron shields and neutron absorbing materials

    International Nuclear Information System (INIS)

    Tsuda, K.; Matsuda, F.; Taniuchi, H.; Yuhara, T.; Iida, T.

    1993-01-01

    A wide range of materials, including polymers and hydrogen-occluded alloys that might be usable as the neutron shielding material were examined. And a wide range of materials, including aluminum alloys that might be usable as the neutron-absorbing material were examined. After screening, the candidate material was determined on the basis of evaluation regarding its adaptabilities as a high-performance neutron-shielding and neutron-absorbing material. This candidate material was manufactured for trial, after which material properties tests, neutron-shielding tests and neutron-absorbing tests were carried out on it. The specifications of this material were thus determined. This research has resulted in materials of good performance; a neutron-shielding material based on ethylene propylene rubber and titanium hydride, and a neutron-absorbing material based on aluminum and titanium hydride. (author)

  10. Study of neutron fields around an intense neutron generator.

    Science.gov (United States)

    Kicka, L; Machrafi, R; Miller, A

    2017-12-01

    Neutron fields in the vicinity of the newly built neutron facility, at the University of Ontario Institute of Technology (UOIT), have been investigated in a series of Monte Carlo simulations and measurements. The facility hosts a P-385 neutron generator based on a deuterium-deuterium fusion reaction. The neutron fluence at different locations around the neutron generator facility has been simulated using MCNPX 2.7E Monte Carlo particle transport program. To characterize neutron fields, three neutron sources were modeled with distributions corresponding to different incident deuteron energies of 90kV, 110kV, and 130kV. Measurements have been carried out to determine the dose rate at locations adjacent to the generator using bubble detectors (BDs). The neutron intensity was evaluated and the total dose rates corresponding to different applied acceleration potentials were estimated at various locations. Copyright © 2017 Elsevier Ltd. All rights reserved.

  11. Imaging with cold neutrons

    International Nuclear Information System (INIS)

    Lehmann, E.H.; Kaestner, A.; Josic, L.; Hartmann, S.; Mannes, D.

    2011-01-01

    Neutrons for imaging purposes are provided mainly from thermal beam lines at suitable facilities around the world. The access to cold neutrons is presently limited to very few places only. However, many challenging options for imaging with cold neutrons have been found out, given by the interaction behavior of the observed materials with neutrons in the cold energy range (3-10 A). For absorbing materials, the interaction probability increases proportionally with the wavelength with the consequence of more contrast but less transmission with cold neutrons. Many materials are predominantly scattering neutrons, in particular most of crystalline structural materials. In these cases, cold neutrons play an important role by covering the energy range of the most important Bragg edges given by the lattice planes of the crystallites. This particular behavior can be used for at least two important aspects-choosing the right energy of the initial beam enables to have a material more or less transparent, and a direct macroscopic visualization of the crystalline structure and its change in a manufacturing process. Since 2006, PSI operates its second beam line for neutron imaging, where cold neutrons are provided from a liquid deuterium cold source (operated at 25 K). It has been designed to cover the most current aspects in neutron imaging research with the help of high flexibility. This has been done with changeable inlet apertures, a turbine based velocity selector, two beam positions and variable detector systems, satisfying the demands of the individual investigation. The most important detection system was found to be a micro-tomography system that enables studies in the presently best spatial resolution. In this case, the high contrast from the sample interaction process and the high detection probability for the cold neutrons combines in an ideal combination for the best possible performance. Recently, it was found out that the energy selective studies might become a

  12. Neutron source multiplication method

    International Nuclear Information System (INIS)

    Clayton, E.D.

    1985-01-01

    Extensive use has been made of neutron source multiplication in thousands of measurements of critical masses and configurations and in subcritical neutron-multiplication measurements in situ that provide data for criticality prevention and control in nuclear materials operations. There is continuing interest in developing reliable methods for monitoring the reactivity, or k/sub eff/, of plant operations, but the required measurements are difficult to carry out and interpret on the far subcritical configurations usually encountered. The relationship between neutron multiplication and reactivity is briefly discussed and data presented to illustrate problems associated with the absolute measurement of neutron multiplication and reactivity in subcritical systems. A number of curves of inverse multiplication have been selected from a variety of experiments showing variations observed in multiplication during the course of critical and subcritical experiments where different methods of reactivity addition were used, with different neutron source detector position locations. Concern is raised regarding the meaning and interpretation of k/sub eff/ as might be measured in a far subcritical system because of the modal effects and spectrum differences that exist between the subcritical and critical systems. Because of this, the calculation of k/sub eff/ identical with unity for the critical assembly, although necessary, may not be sufficient to assure safety margins in calculations pertaining to far subcritical systems. Further study is needed on the interpretation and meaning of k/sub eff/ in the far subcritical system

  13. Neutron shielding material

    International Nuclear Information System (INIS)

    Nodaka, M.; Iida, T.; Taniuchi, H.; Yosimura, K.; Nagahama, H.

    1993-01-01

    From among the neutron shielding materials of the 'kobesh' series developed by Kobe Steel, Ltd. for transport and storage packagings, silicon rubber base type material has been tested for several items with a view to practical application and official authorization, and in order to determine its adaptability to actual vessels. Silicon rubber base type 'kobesh SR-T01' is a material in which, from among the silicone rubber based neutron shielding materials, the hydrogen content is highest and the boron content is most optimized. Its neutron shielding capability has been already described in the previous report (Taniuchi, 1986). The following tests were carried out to determine suitability for practical application; 1) Long-term thermal stability test 2) Pouring test on an actual-scale model 3) Fire test The experimental results showed that the silicone rubber based neutron shielding material has good neutron shielding capability and high long-term fire resistance, and that it can be applied to the advanced transport packaging. (author)

  14. Fast neutron dosimetry

    International Nuclear Information System (INIS)

    DeLuca, P.M. Jr.; Pearson, D.W.

    1991-01-01

    During 1988--1990 the magnetic resonance dosimetry project was completed, as were the 250 MeV proton shielding measurements. The first cellular experiment using human cells in vitro at the 1 GeV electron storage ring was also accomplished. More detail may be found in DOE Report number-sign DOE/EV/60417-002 and the open literature cited in the individual progress subsections. We report Kinetic Energy Released in Matter (KERMA), factor measurements in several elements of critical importance to neutron radiation therapy and radiation protection for space habitation and exploration for neutron energies below 30 MeV. The results of this effort provide the only direct measurements of the oxygen and magnesium kerma factors above 20 MeV neutron energy, and the only measurements of the iron kerma factor above 15 MeV. They provide data of immediate relevance to neutron radiotherapy and impose strict criteria for normalizing and testing nuclear models used to calculate kerma factors at higher neutron energies

  15. Neutron halos in hypernuclei

    CERN Document Server

    Lue, H F; Meng, J; Zhou, S G

    2003-01-01

    Properties of single-LAMBDA and double-LAMBDA hypernuclei for even-N Ca isotopes ranging from the proton dripline to the neutron dripline are studied using the relativistic continuum Hartree-Bogolyubov theory with a zero-range pairing interaction. Compared with ordinary nuclei, the addition of one or two LAMBDA-hyperons lowers the Fermi level. The predicted neutron dripline nuclei are, respectively, sup 7 sup 5 subLAMBDA Ca and sup 7 sup 6 sub 2 subLAMBDA Ca, as the additional attractive force provided by the LAMBDA-N interaction shifts nuclei from outside to inside the dripline. Therefore, the last bound hypernuclei have two more neutrons than the corresponding ordinary nuclei. Based on the analysis of two-neutron separation energies, neutron single-particle energy levels, the contribution of continuum and nucleon density distribution, giant halo phenomena due to the pairing correlation, and the contribution from the continuum are suggested to exist in Ca hypernuclei similar to those that appear in ordinary ...

  16. Storing of free neutrons

    International Nuclear Information System (INIS)

    Trinks, U.

    1978-12-01

    The applied method makes use of the interaction between the magnetic moment μ vector of the neutron and a magnetic field B vector. By means of superconducting magnets there can easily be achieved potential walls of μ B approximately 2 x 10 -7 eV. The principle of magnetic storing was first used for the storage ring NESTOR and showed immediate success: the stored neutrons decreased exponentially with a time constant tau = (907 +- 70) sec corresponding to the natural lifetime of the neutrons within the statistical errors. This means that there occurred no measurable additional losses (e.g. by resonance excitation) Neutrons therefore could be observed in the storage ring during about 5 half-lives (in principle of course longer, too). The orbit dynamics for neutrons in the storage ring is smilar to that in circular accelerators for charged particles. It is so well understood that the problem of the storage ring for uncharged particles (with magnetic moment) may be considered to e solved. (orig./HSI) [de

  17. Neutrons for sale

    International Nuclear Information System (INIS)

    Daviss, B.

    1997-01-01

    A fusion machine, in the form of a sphere small enough to fit on a desktop, is described. It can be switched on and off at will and produces virtually no radioactive waste. The fusion sphere creates an electric potential which forms deuterium ions into beams and accelerates them towards the centre. Nuclei of deuterium inside a central spherical wire grid fuse to create neutrons, helium -3 and traces of hydrogen and tritium. The rudimentary device is expected to go on sale in a commercial form in 1998. The immediate applications are those which require a yield of neutrons falling in the range 10 7 to 10 10 neutrons per second. This is expected to be well within the capability of the sphere and would allow neutron activation analysis to be carried out for the detection of hidden high explosives in airport baggage checks, or impurities in ores as they are mined for example. With higher neutron yields other applications such as the treatment of tumours could become viable but the technical problems are likely to multiply with the increasing yields. (UK)

  18. Neutrons and art

    International Nuclear Information System (INIS)

    Panczyk, E.; Walis, L.

    2004-01-01

    Following modern trends in art objects connoisseurship, through examination of the structure of art objects supports traditional studies conducted by art historians based on composition, iconographic and stylistic comparisons. It must be emphasized that complete technological examinations are carried out by means of comprehensive physical and chemical studies. Among various methods used for the examination of art objects, methods which apply neutrons such as instrumental neutron activation analysis (INAA), prompt gamma activation analysis (PGAA) and neutron-induced autoradiography are crucial due to their high sensitivity, reproducibility and capability of simultaneous determination of several tens of elements. Systematic studies on art objects using instrumental neutron activation analysis and neutron autoradiography have been carried out in the institute of Nuclear Chemistry and Technology. It was possible to accumulate a number of essential data on the concentration of trace elements particularly in chalk grounds and pigments (such as lead white, lead-tin yellow, smalt), Chinese porcelain, Thai ceramics, silver denarius, jewellery made of copper alloys, as well as in the clay fillings of Egyptian mummies. The above mentioned examination of art objects prior to their conservation helps to determine precisely the materials used in the process of creating art objects, as well as to identify the appropriate place of origin of particular materials. (author)

  19. Neutron instrumentation system

    International Nuclear Information System (INIS)

    Akiyama, Takao; Arita, Setsuo; Yuchi, Hiroyuki

    1989-01-01

    The neutron instrumentation system of this invention can greatly reduce the possibility that the shutdown flux is increased greater than a predetermiend value to cause scram due to vibrations caused by earthquakes or shocks in the neutron instrumentation system without injuring the reactor safety. That is, a sensor having a zero sensitivity to a neutron flux which is an object to be detected by the sensor (dummy sensor) is used together with a conventional sensor (a sensor having predetermined sensitivity to a neutron flux as an object to be measured ----- true sensor). Further, identical signal transmission cables, connector and the signal processing circuits are used for both of true sensor and the dummy sensor. The signal from the dummy sensor is subtracted from the signal from the true sensor at the output of the signal processing circuit. Since the output of the dummy sensor is zero during normal operation, the subtracted value is the same as the value from the true sensor. If the true sensor causes an output with the reason other than the neutron flux, this is outputted also from the dummy sensor but does not appear in the subtracted value. (I.S.)

  20. The Advanced Neutron Source

    International Nuclear Information System (INIS)

    Peretz, F.J.

    1990-01-01

    The Advanced Neutron Source (ANS) is to be a multipurpose neutron research center, constructed around a high-flux reactor now being designed at the Oak Ridge National Laboratory (ORNL). Its primary purpose is to place the United States in the forefront of neutron scattering in the twenty-first century. Other research programs include nuclear and fundamental physics, isotope production, materials irradiation, and analytical chemistry. The ANS will be a unique and invaluable research tool because of the unprecedented neutron flux available from the high-intensity research reactor. But this reactor would be ineffective without world-class research facilities that allow the fullest utilization of the available neutrons. And, in turn, those research facilities will not produce new and exciting science without a broad population of users from all parts of the nation and the world, placed in a stimulating environment in which experiments can be effectively conducted and in which scientific exchange is encouraged. This paper discusses the measures being taken to ensure that the design of the ANS focuses not only on the reactor, but on providing the experiment and user support facilities needed to allow its effective use

  1. SUSANS With Polarized Neutrons.

    Science.gov (United States)

    Wagh, Apoorva G; Rakhecha, Veer Chand; Strobl, Makus; Treimer, Wolfgang

    2005-01-01

    Super Ultra-Small Angle Neutron Scattering (SUSANS) studies over wave vector transfers of 10(-4) nm(-1) to 10(-3) nm(-1) afford information on micrometer-size agglomerates in samples. Using a right-angled magnetic air prism, we have achieved a separation of ≈10 arcsec between ≈2 arcsec wide up- and down-spin peaks of 0.54 nm neutrons. The SUSANS instrument has thus been equipped with the polarized neutron option. The samples are placed in a uniform vertical field of 8.8 × 10(4) A/m (1.1 kOe). Several magnetic alloy ribbon samples broaden the up-spin neutron peak significantly over the ±1.3 × 10(-3) nm(-1) range, while leaving the down-spin peak essentially unaltered. Fourier transforms of these SUSANS spectra corrected for the instrument resolution, yield micrometer-range pair distribution functions for up- and down-spin neutrons as well as the nuclear and magnetic scattering length density distributions in the samples.

  2. A study on aluminum determination in environmental samples by Neutron Activation Analysis; Estudo sobre determinação de alumínio em amostras ambientais pelo método de análise por ativação com nêutrons

    Energy Technology Data Exchange (ETDEWEB)

    Noyori, Amanda

    2017-07-01

    Aluminum determinations are of great interest since this element is toxic to humans and it is widely distributed in the environment. Besides, the determinations of this element by conventional analytical methods present difficulties due to sample contamination during the analyses. Neutron activation analysis (NAA) for Al determination presents advantages of fast analyses and of high sensitivity. However, NAA of Al does present problems of P and Si nuclear reaction interferences. Aluminum is determined by measuring {sup 28}Al, formed in the reaction {sup 27}Al (n, γ) {sup 28}Al, the same radioisotope formed in reactions {sup 31}P (n, α) {sup 28}Al and {sup 28}Si (n, p) {sup 28}Al. The purpose of this study was to determine Al in environmental samples by NAA correcting these interferences using correction factors, and determining P and Si concentrations in the samples. In this study, certified reference materials and biomonitor samples (tree barks and lichen) were analyzed. Experimental procedure consisted of irradiating an aliquot of the sample at the IEA-R1 nuclear research reactor together with Al standard, followed by gamma ray spectrometry. Phosphorus was determined by measuring beta radiation of {sup 32}P using a Geiger-Müller counter. Silicon was determined by epithermal neutron activation analysis and measuring {sup 29}Al formed in the reaction {sup 29}Si (n, p){sup 29}Al. Results obtained in the determination of Al, P and Si in the certified reference materials showed good precision and accuracy with |Z-score| ≤ 2. Aluminum results in the biomonitor samples varied from to 253 to 15783 μg g{sup -1}. In the case of P its concentrations varied from 283 to 1946 μg g{sup -1}. Silicon determinations in biomonitors varied from 0.11 to 7.8 %. The interference contribution rates in the analyses of the biomonitor samples were of the order of 2.0 % and this contribution depends on the relation between concentrations of interfering elements and of Al in the

  3. Neutron nuclear physics under the neutron science project

    Energy Technology Data Exchange (ETDEWEB)

    Chiba, Satoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-11-01

    The concept of fast neutron physics facility in the Neutron Science Research project is described. This facility makes use of an ultra-short proton pulse (width < 1 ns) for fast neutron time-of-flight works. The current design is based on an assumption of the maximum proton current of 100 {mu}A. Available neutron fluence and energy resolution are explained. Some of the research subjects to be performed at this facility are discussed. (author)

  4. Study of the distribution characteristics of rare earth elements in Solanum lycocarpum from different tropical environments in Brazil by neutron activation analysis; Estudo das caracteristicas de distribuicao de elementos terras raras em Solanum lycocarpum em diferentes ambientes tropicais do Brasil por ativacao neutronica

    Energy Technology Data Exchange (ETDEWEB)

    Maria, Sheila Piorino

    2001-07-01

    In this work, the concentration of eight rare earth elements (REE), La, Ce, Nd, Sm, Eu, Tb, Yb and Lu, was determined by neutron activation analysis (INAA), in plant leaves of Solanum lycocarpum. This species is a typical Brazilian 'cerrado' plant, widely distributed in Brazil. The analysis of the plant reference materials CRM Pine Needles (NIST 1575) and Spruce Needles (BCR 101) proved that the methodology applied was sufficiently accurate and precise for the determination of REE in plants. In order to better evaluate the uptake of the REE from the soil to the plant, the host soil was also analyzed by ESiAA. The studied areas were Salitre, MG, Serra do Cipo, MG, Lagoa da Pampulha and Mangabeiras, in Belo Horizonte, MG, and Cerrado de Emas, in Pirassununga, SP. The results were analyzed through the calculation of transfer factors soil-plant and by using diagrams normalized to chondrites. The data obtained showed different transfer factors from soil to plant as the subtract changes. Similar distribution patterns for the soil and the plant were obtained in all the studied sites, presenting an enrichment of the light REE (La to Sm), in contrast to the heavy REE (Eu to Lu), less absorbed. These results indicate that the light REE remain available to the plant in the more superficial soil layers. The similarity between the distribution patterns indicates a typical REE absorption by this species, in spite of the significant differences in the substratum . (author)

  5. Study on water-sediment interaction in samples from Rio das Velhas - Minas Gerais State - Brazil using instrumental neutron activation analysis, and argon plasma coupled mass spectroscopy; Estudo da interacao agua-sedimento em amostras do Rio das Velhas - MG utilizando os metodos: analise por ativacao neutronica instrumental (INAA) e espectrometria de massa acoplada a um plasma de argonio (ICP-MS)

    Energy Technology Data Exchange (ETDEWEB)

    Veado, Maria Adelaide R.V.; Oliveira, Arno H. de [Minas Gerais Univ., Belo Horizonte, MG (Brazil). Dept. de Engenharia Nuclear; Revel, G.; Pinte, G. [CEA Centre d`Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Lab. d`Analyse par Activation Pierre Sue; Toulhoat, P. [CEA Centre d`Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Unite Mixte de Recherche Analyse et Environnement

    1999-11-01

    Sorption of the metallic elements in aqueous solutions in surface of the hydroxides affects the transport of heavy elements in the freshwaters. Sorption and the chemistry of the hydroxides are important studies for knowledge in geology, waters and waste treatment, and environment studies. In the industrial mining region areas, the river surface waters are subject to modifications in its physical and chemistries properties: pH, DBO, conductivity and alkalinity. Instrumental neutron activation analysis and inductively coupled plasma-mass spectrometry (ICP-MS), have ben used for the determination of toxic heavy metals and others pollutants in the Das Velhas river in State of Minas Gerais, in south-east Brazil. Water samples were collected with acidification on site, which provoked a change of its natural pH. Consequently, metallic elements associated to hydroxides and to particles in suspension were liberated. The objective of this paper is to show the different behavior of any elements, in water of Das Velhas river, with relation of its chemical forms (cations or anions), the solubility degree, the pH and the presence of rare earth elements. (author) 11 refs., 10 figs.; e-mail: adelaide at nuclear.ufmg.br; heeren at nuclear.ufmg.br; grevel at drecam.cea.fr; pierre.toulhoat at cea.fr

  6. Level gauge using neutron radiation

    International Nuclear Information System (INIS)

    Mathew, P.J.

    1985-01-01

    Apparatus for determining the level of a solid or liquid material in a container comprises: a vertical guide within or alongside the container; a sensor positioned within the guide; means for moving the sensor along the guide; and means for monitoring the position of the sensor. The sensor comprises a source of fast neutrons, a detector for thermal neutrons, and a body of a neutron moderating material in close proximity to the detector. Thermal neutrons produced by fast neutron irradiation of the solid or liquid material, or thermal neutrons produced by irradiation of the neutron-moderating material by fast or epithermal neutrons reflected by the solid or liquid material, are detected when the sensor is positioned at or below the level of the material in the container

  7. Neutron radiography with the cyclotron

    International Nuclear Information System (INIS)

    Tazawa, Shuichi; Asada, Yorihisa; Yano, Munehiko; Nakanii, Takehiko.

    1985-01-01

    Neutron radiography is well recognized as a powerful tool in nondestructive testing, but not widely used yet owing to lack of high intense thermal neutron source convenient for practical use. This article presents a new neutron radiograph facility, utilizing a sub-compact cyclotron as neutron source and is equipped with vertical and horizontal irradiation ports. The article describes a series of experiments, we conducted using beams of a variable energy cyclotron at Tohoku University to investigate the characteristics of thermal neutron obtained from 9 Be(p, n) reaction and thermalized by elastic scattering process. The article also describes a computer simulation of neutron moderator to analyze conditions getting maximal thermal neutron flux. Further, some of practical neutron radiograph examinations of aero-space components and museum art objects of classic bronze mirror and an attempt realizing real time imaging technique, are introduced in the article. (author)

  8. Nuclear fusion and neutron processes

    International Nuclear Information System (INIS)

    Orlov, V.V.; Shatalov, G.E.; Sherstnev, K.E.

    1984-01-01

    Problems of providing development of the design of an experimental fusion reactor with necessary neutron-physical data are discussed. Isotope composition of spent fuel in the blanket of a hybride fusion reactor (HFR) is given. Neutron balance of the reactor with Li-blanket and neutron balance of the reactor with Pb-multiplier are disclosed. A simplified scheme of neutron and energy balance in the HFR blanket is given. Development and construction of the experimental power reactor is shown to become the nearest problem of the UTS program. Alongside with other complex physical and technical problems solution of this problem requires realization of a wide program of neutron-physical investigations including measurements with required accuracy of neutron cross sections, development of methodical, program and constant basis of neutron calculations and macroscopic experiments on neutron sources

  9. Recent advances in neutron tomography

    International Nuclear Information System (INIS)

    McFarland, E.; Massachusetts Inst. of Technology, Cambridge, MA; Lanza, R.

    1993-01-01

    Neutron imaging has been shown to be an excellent imaging tool for many nondestructive evaluation applications. Significantly improved contrast over X-ray images is possible for materials commonly found in engineering assemblies. The major limitations have been the neutron source and detection. A low cost, position sensitive neutron tomography detector system has been designed and built based on an electro-optical detector system using a LiF-ZnS scintillator screen and a cooled charge coupled device. This detector system can be used for neutron radiography as well as two and three-dimensional neutron tomography. Calculated performance of the system predicted near-quantum efficiency for position sensitive neutron detection. Experimental data was recently taken using this system at McClellan Air Force Base, Air Logistics Center, Sacramento, CA. With increased availability of low cost neutron sources and advanced image processing, neutron tomography will become an increasingly important nondestructive imaging method

  10. Virtual neutron scattering experiments

    DEFF Research Database (Denmark)

    Overgaard, Julie Hougaard; Bruun, Jesper; May, Michael

    2016-01-01

    We describe how virtual experiments can be utilized in a learning design that prepares students for hands-on experiments at large-scale facilities. We illustrate the design by showing how virtual experiments are used at the Niels Bohr Institute in a master level course on neutron scattering....... In the last week of the course, students travel to a large-scale neutron scattering facility to perform real neutron scattering experiments. Through student interviews and survey answers, we argue, that the virtual training prepares the students to engage more fruitfully with experiments by letting them focus...... on physics and data rather than the overwhelming instrumentation. We argue that this is because they can transfer their virtual experimental experience to the real-life situation. However, we also find that learning is still situated in the sense that only knowledge of particular experiments is transferred...

  11. The neutron discovery

    International Nuclear Information System (INIS)

    Six, J.

    1987-01-01

    The neutron: who had first the idea, who discovered it, who established its main properties. To these apparently simple questions, multiple answers exist. The progressive discovery of the neutron is a marvellous illustration of some characteristics of the scientific research, where the unforeseen may be combined with the expected. This discovery is replaced in the context of the 1930's scientific effervescence that succeeded the revolutionary introduction of quantum mechanics. This book describes the works of Bothe, the Joliot-Curie and Chadwick which led to the neutron in an unexpected way. A historical analysis allows to give a new interpretation on the hypothesis suggested by the Joliot-Curie. Some texts of these days will help the reader to revive this fascinating story [fr

  12. Gadolinium neutron capture therapy

    International Nuclear Information System (INIS)

    Akine, Yasuyuki; Tokita, Nobuhiko; Tokuuye, Koichi; Satoh, Michinao; Churei, Hisahiko

    1993-01-01

    Gadolinium neutron capture therapy makes use of photons and electrons produced by nuclear reactions between gadolinium and lower-energy neutrons which occur within the tumor. The results of our studies have shown that its radiation effect is mostly of low LET and that the electrons are the significant component in the over-all dose. The dose from gadolinium neutron capture reactions does not seem to increase in proportion to the gadolinium concentration, and the Gd-157 concentration of about 100 μg/ml appears most optimal for therapy. Close contact between gadolinium and the cell is not necessarily required for cell inactivation, however, the effect of electrons released from intracellular gadolinium may be significant. Experimental studies on tumor-bearing mice and rabbits have shown that this is a very promising modality though further improvements in gadolinium delivery to tumors are needed. (author)

  13. Catalogue of neutron spectra

    International Nuclear Information System (INIS)

    Buxerolle, M.; Massoutie, M.; Kurdjian, J.

    1987-09-01

    Neutron dosimetry problems have arisen as a result of developments in the applications of nuclear energy. The largest number of possible irradiation situations has been collected: they are presented in the form of a compilation of 44 neutron spectra. Diagrams show the variations of energy fluence and energy fluence weighted by the dose equivalent/fluence conversion factor, with the logarithm of the corresponding energy. The equivalent dose distributions are presented as percentages for the following energy bins: 0.01 eV/0.5 eV/50 keV/1 MeV/5 MeV/15 MeV. The dose equivalent, the mean energy and the effective energy for the dose equivalent for 1 neutron cm -2 are also given [fr

  14. CARBON NEUTRON STAR ATMOSPHERES

    International Nuclear Information System (INIS)

    Suleimanov, V. F.; Klochkov, D.; Werner, K.; Pavlov, G. G.

    2014-01-01

    The accuracy of measuring the basic parameters of neutron stars is limited in particular by uncertainties in the chemical composition of their atmospheres. For example, the atmospheres of thermally emitting neutron stars in supernova remnants might have exotic chemical compositions, and for one of them, the neutron star in Cas A, a pure carbon atmosphere has recently been suggested by Ho and Heinke. To test this composition for other similar sources, a publicly available detailed grid of the carbon model atmosphere spectra is needed. We have computed this grid using the standard local thermodynamic equilibrium approximation and assuming that the magnetic field does not exceed 10 8  G. The opacities and pressure ionization effects are calculated using the Opacity Project approach. We describe the properties of our models and investigate the impact of the adopted assumptions and approximations on the emergent spectra

  15. Multidisk neutron velocity selectors

    International Nuclear Information System (INIS)

    Hammouda, B.

    1992-01-01

    Helical multidisk velocity selectors used for neutron scattering applications have been analyzed and tested experimentally. Design and performance considerations are discussed along with simple explanation of the basic concept. A simple progression is used for the inter-disk spacing in the 'Rosta' design. Ray tracing computer investigations are presented in order to assess the 'coverage' (how many absorbing layers are stacked along the path of 'wrong' wavelength neutrons) and the relative number of neutrons absorbed in each disk (and therefore the relative amount of gamma radiation emitted from each disk). We discuss whether a multidisk velocity selector can be operated in the 'reverse' configuration (i.e. the selector is turned by 180 0 around a vertical axis with the rotor spun in the reverse direction). Experimental tests and calibration of a multidisk selector are reported together with evidence that a multidisk selector can be operated in the 'reverse' configuration. (orig.)

  16. Spherical neutron generator

    Science.gov (United States)

    Leung, Ka-Ngo

    2006-11-21

    A spherical neutron generator is formed with a small spherical target and a spherical shell RF-driven plasma ion source surrounding the target. A deuterium (or deuterium and tritium) ion plasma is produced by RF excitation in the plasma ion source using an RF antenna. The plasma generation region is a spherical shell between an outer chamber and an inner extraction electrode. A spherical neutron generating target is at the center of the chamber and is biased negatively with respect to the extraction electrode which contains many holes. Ions passing through the holes in the extraction electrode are focused onto the target which produces neutrons by D-D or D-T reactions.

  17. Burnable neutron absorbers

    International Nuclear Information System (INIS)

    Radford, K.C.; Carlson, W.G.

    1983-01-01

    A neutron-absorber body for use in burnable poison rods in a nuclear reactor. The body is composed of a matrix of Al 2 O 3 containing B 4 C, the neutron absorber. Areas of high density polycrystalline Al 2 O 3 particles are predominantly encircled by pores in some of which there are B 4 C particles. This body is produced by initially spray drying a slurry of A1 2 O 3 powder to which a binder has been added. The powder of agglomerated spheres of the A1 2 O 3 with the binder are dry mixed with B 4 C powder. The mixed powder is formed into a green body by isostatic pressure and the green body is sintered. The sintered body is processed to form the neutron-absorber body. In this case the B 4 C particles are separate from the spheres resulting from the spray drying instead of being embedded in the sphere

  18. Neutron activation analysis

    International Nuclear Information System (INIS)

    Borsaru, M.; Eisler, P.L.

    1981-01-01

    A method of simultaneously analysing the aluminium and silicon content of a sample of material is claimed. The method comprises the following steps: (1) irradiating the sample with fast neutrons; (2) monitoring the thermal neutron flux within the sample; (3) monitoring the gamma radiation from the irradiated sample at energies of 1.78 MeV and 1.015 and/or 0.844 MeV; (4) using the monitored gamma radiation at 1.015 and/or 0.844 MeV to estimate the aluminium content of the sample; and (5) using the monitored gamma radiation at 1.78 MeV, compensated by the gamma radiation at 1.78 MeV due to the thermal neutron reaction with the estimated aluminium in the sample to estimate the silicon content

  19. Semiconductor research with reactor neutrons

    International Nuclear Information System (INIS)

    Kimura, Itsuro

    1992-01-01

    Reactor neutrons play an important role for characterization of semiconductor materials as same as other advanced materials. On the other hand reactor neutrons bring about not only malignant irradiation effects called radiation damage, but also useful effects such as neutron transmutation doping and defect formation for opto-electronics. Research works on semiconductor materials with the reactor neutrons of the Kyoto University Reactor (KUR) are briefly reviewed. In this review, a stress is laid on the present author's works. (author)

  20. Corrosion resistant neutron absorbing coatings

    Science.gov (United States)

    Choi, Jor-Shan [El Cerrito, CA; Farmer, Joseph C [Tracy, CA; Lee, Chuck K [Hayward, CA; Walker, Jeffrey [Gaithersburg, MD; Russell, Paige [Las Vegas, NV; Kirkwood, Jon [Saint Leonard, MD; Yang, Nancy [Lafayette, CA; Champagne, Victor [Oxford, PA

    2012-05-29

    A method of forming a corrosion resistant neutron absorbing coating comprising the steps of spray or deposition or sputtering or welding processing to form a composite material made of a spray or deposition or sputtering or welding material, and a neutron absorbing material. Also a corrosion resistant neutron absorbing coating comprising a composite material made of a spray or deposition or sputtering or welding material, and a neutron absorbing material.

  1. Neutron capture in borehole logging

    International Nuclear Information System (INIS)

    Randall, R.R.

    1981-01-01

    The use is described of a pulsed source of fast neutrons and a radiation detector to measure the thermal neutron population decay rate in a well logging instrument. The macroscopic neutron absorption cross-section is calculated by taking the natural logarithm of the ratio of the detected radiation counts occurring within two measurement intervals of fixed duration and starting at a fixed time after a neutron burst. (U.K.)

  2. Compact neutron flux monitor

    International Nuclear Information System (INIS)

    Madhavi, V.; Phatak, P.R.; Bahadur, C.; Bayala, A.K.; Jakati, R.K.; Sathian, V.

    2003-01-01

    Full text: A compact size neutron flux monitor has been developed incorporating standard boards developed for smart radiation monitors. The sensitivity of the monitors is 0.4cps/nV. It has been tested up to 2075 nV flux with standard neutron sources. It shows convincing results even in high flux areas like 6m away from the accelerator in RMC (Parel) for 106/107 nV. These monitors have a focal and remote display, alarm function with potential free contacts for centralized control and additional provision of connectivity via RS485/Ethernet. This paper describes the construction, working and results of the above flux monitor

  3. Neutron absorbing article

    International Nuclear Information System (INIS)

    Naum, R.G.; Owens, D.P.; Dooker, G.I.

    1981-01-01

    A neutron-absorbing article suitable for use in spent fuel racks is described. It comprises boron carbide particles, diluent particles, and a phenolic polymer cured to a continuous matrix. The diluent may be silicon carbide, graphite, amorphous carbon, alumina, or silica. The combined boron carbide-diluent phase contains no more than 2 percent B 2 O 3 , and the neutron-absorbing article contains from 20 to 40 percent phenol resin. The ratio of boron carbide to diluent particles is in the range 1:9 to 9:1

  4. Fast neutron dosimetry

    International Nuclear Information System (INIS)

    DeLuca, P.M. Jr.; Pearson, D.W.

    1992-01-01

    This progress report concentrates on two major areas of dosimetry research: measurement of fast neutron kerma factors for several elements for monochromatic and white spectrum neutron fields and determination of the response of thermoluminescent phosphors to various ultra-soft X-ray energies and beta-rays. Dr. Zhixin Zhou from the Shanghai Institute of Radiation Medicine, People's Republic of China brought with him special expertise in the fabrication and use of ultra-thin TLD materials. Such materials are not available in the USA. The rather unique properties of these materials were investigated during this grant period

  5. MCNP neutron benchmarks

    International Nuclear Information System (INIS)

    Hendricks, J.S.; Whalen, D.J.; Cardon, D.A.; Uhle, J.L.

    1991-01-01

    Over 50 neutron benchmark calculations have recently been completed as part of an ongoing program to validate the MCNP Monte Carlo radiation transport code. The new and significant aspects of this work are as follows: These calculations are the first attempt at a validation program for MCNP and the first official benchmarking of version 4 of the code. We believe the chosen set of benchmarks is a comprehensive set that may be useful for benchmarking other radiation transport codes and data libraries. These calculations provide insight into how well neutron transport calculations can be expected to model a wide variety of problems

  6. Slow neutron scattering experiments

    International Nuclear Information System (INIS)

    Moon, R.M.

    1985-01-01

    Neutron scattering is a versatile technique that has been successfully applied to condensed-matter physics, biology, polymer science, chemistry, and materials science. The United States lost its leadership role in this field to Western Europe about 10 years ago. Recently, a modest investment in the United States in new facilities and a positive attitude on the part of the national laboratories toward outside users have resulted in a dramatic increase in the number of US scientists involved in neutron scattering research. Plans are being made for investments in new and improved facilities that could return the leadership role to the United States. 23 references, 4 figures, 3 tables

  7. Neutron optical potentials

    International Nuclear Information System (INIS)

    Wilmore, D.; Hodgson, P.E.

    1976-01-01

    The purpose of this paper is to provide a guide to the use of optical model computer programs to analyse and calculate neutron data. After a brief discussion of the physical basis of the optical model a survey is given of the most widely used optical model and Hauser-Feshbach computer programs. The range of applicability and reliability of the major optical potentials proposed is assessed by comparison with available experimental data and some observations and suggestions are made for the optimum choice of optical potentials for given purposes of neutron data calculations. (author)

  8. Nuclear physics and neutronics

    International Nuclear Information System (INIS)

    Paya, D.

    1997-01-01

    After a brief review of the beginnings of the nuclear reaction physics in France in the 40's and 50's, the experimentation neutronics and nuclear physics studies are related and their uses presented, which aims were to provide data for the study of the various reactor concepts and to study fundamental physics. Progressively, pure nuclear physics lost its links with neutronics, and its influence decreases more or less. Long life radioactive waste reprocessing is an important domain where it could regain its contribution

  9. Neutron detector assembly

    International Nuclear Information System (INIS)

    Hanai, Koi; Shirayama, Shinpei.

    1978-01-01

    Purpose: To prevent gamma-ray from leaking externally passing through the inside of a neutron detector assembly. Constitution: In a neutron detector assembly having a protection pipe formed with an enlarged diameter portion which serves also as a spacer, partition plates with predetermined width are disposed at the upper and the lower portions in this expanded portion. A lot of metal particles are filled into spaces formed by the partition plates. In such a structure, the metal particles well-absorb the gamma-rays from above and convert them into heat to provide shielding for the gamma-rays. (Horiuchi, T.)

  10. Fast neutron dosimetry

    International Nuclear Information System (INIS)

    DeLuca, P.M. Jr.; Pearson, D.W.

    1993-01-01

    Research concentrated on three major areas during the last twelve months: (1) investigations of energy fluence and absorbed dose measurements using crystalline and hot pressed TLD materials exposes to ultrasoft beams of photons, (2) fast neutron kerma factor measurements for several important elements as well as NE-213 scintillation material response function determinations at the intense ''white'' source available at the WNR facility at LAMPF, and (3) kerma factor ratio determinations for carbon and oxygen to A-150 tissue equivalent plastic at the clinical fast neutron radiation facility at Harper Hospital, Detroit, MI. Progress summary reports of these efforts are given in this report

  11. GUIDE FOR POLARIZED NEUTRONS

    Science.gov (United States)

    Sailor, V.L.; Aichroth, R.W.

    1962-12-01

    The plane of polarization of a beam of polarized neutrons is changed by this invention, and the plane can be flipped back and forth quicitly in two directions in a trouble-free manner. The invention comprises a guide having a plurality of oppositely directed magnets forming a gap for the neutron beam and the gaps are spaced longitudinally in a spiral along the beam at small stepped angles. When it is desired to flip the plane of polarization the magnets are suitably rotated to change the direction of the spiral of the gaps. (AEC)

  12. Imaging with Polarized Neutrons

    Directory of Open Access Journals (Sweden)

    Nikolay Kardjilov

    2018-01-01

    Full Text Available Owing to their zero charge, neutrons are able to pass through thick layers of matter (typically several centimeters while being sensitive to magnetic fields due to their intrinsic magnetic moment. Therefore, in addition to the conventional attenuation contrast image, the magnetic field inside and around a sample can be visualized by detecting changes of polarization in a transmitted beam. The method is based on the spatially resolved measurement of the cumulative precession angles of a collimated, polarized, monochromatic neutron beam that traverses a magnetic field or sample.

  13. Neutron physics with accelerators

    Science.gov (United States)

    Colonna, N.; Gunsing, F.; Käppeler, F.

    2018-07-01

    Neutron-induced nuclear reactions are of key importance for a variety of applications in basic and applied science. Apart from nuclear reactors, accelerator-based neutron sources play a major role in experimental studies, especially for the determination of reaction cross sections over a wide energy span from sub-thermal to GeV energies. After an overview of present and upcoming facilities, this article deals with state-of-the-art detectors and equipment, including the often difficult sample problem. These issues are illustrated at selected examples of measurements for nuclear astrophysics and reactor technology with emphasis on their intertwined relations.

  14. Investigation of Response of Several Neutron Surveymeters by a DT Neutron Generator

    International Nuclear Information System (INIS)

    Kim, Sang In; Jang, In Su; Kim, Jang Lyul; Lee, Jung IL; Kim, Bong Hwan

    2012-01-01

    Several neutron measuring devices were tested under the neutron fields characterized with two distinct kinds of thermal and fast neutron spectrum. These neutron fields were constructed by the mixing of both thermal neutron fields and fast neutron fields. The thermal neutron field was constructed using by a graphite pile with eight AmBe neutron sources. The fast neutron field of 14 MeV was made by a DT neutron generator. In order to change the fraction of fast neutron fluence rate in each neutron fields, a neutron generator was placed in the thermal neutron field at 50 cm and 150 cm from the reference position. The polyethylene neutron collimator was used to make moderated 14 MeV neutron field. These neutron spectra were measured by using a Bonner sphere system with an LiI scintillator, and dosimetric quantities delivered to neutron surveymeters were determined from these measurement results.

  15. Esporotricosis diagnosticada por el laboratorio

    Directory of Open Access Journals (Sweden)

    Nelly Ordóñez

    1989-06-01

    Full Text Available De 1976 a 1989 se han diagnosticado 40 casos de esporotricosis en el laboratorio de Micología del Instituto Nacional de Salud. La enfermedad se presentó en pacientes entre 4 y 52 años y tuvo predilección por el sexo masculino: 35 de 40 (87,5%; las formas clínicas más frecuentes fueron la cutánea fija, 18 de 40 (45%, y la linfocutánea, 17 de 40 (42,5%, con localización mayor en miembros superiores, 18 de 40 (45%. El diagnóstico se estableció por el aislamiento del Sporothrix schenckii en 35 de 38 pacientes (92%; los otros dos pacientes se diagnosticaron empleando otras técnicas: inmunofluorescencia directa, intradermorreacción y aglutinación en tubo.

  16. New electronically black neutron detectors

    International Nuclear Information System (INIS)

    Drake, D.M.; Feldman, W.C.; Hurlbut, C.

    1986-03-01

    Two neutron detectors are described that can function in a continuous radiation background. Both detectors identify neutrons by recording a proton recoil pulse followed by a characteristic capture pulse. This peculiar signature indicates that the neutron has lost all its energy in the scintillator. Resolutions and efficiencies have been measured for both detectors

  17. Introductory theory of neutron scattering

    International Nuclear Information System (INIS)

    Gunn, J.M.F.

    1986-12-01

    The paper comprises a set of six lecture notes which were delivered to the summer school on 'Neutron Scattering at a pulsed source', Rutherford Laboratory, United Kingdom, 1986. The lectures concern the physical principles of neutron scattering. The topics of the lectures include: diffraction, incoherent inelastic scattering, connection with the Schroedinger equation, magnetic scattering, coherent inelastic scattering, and surfaces and neutron optics. (UK)

  18. Educational activities for neutron sciences

    International Nuclear Information System (INIS)

    Hiraka, Haruhiro; Ohoyama, Kenji; Iwasa, Kazuaki

    2011-01-01

    Since now we have several world-leading neutron science facilities in Japan, enlightenment activities for introducing neutron sciences, for example, to young people is an indispensable issue. Hereafter, we will report present status of the activities based on collaborations between universities and neutron facilities. A few suggestions for future educational activity of JSNS are also shown. (author)

  19. Neutron guides and scientific neutron equipment at CILAS/GMI

    International Nuclear Information System (INIS)

    Gautier-Picard, P.

    2003-01-01

    CILAS company is the world's leading supplier of complete neutron guides systems. The neutron optics with multilayer coatings produced by CILAS have become an international standard for neutron beam transportation in the modern research institutes. During the last 30 years, CILAS designed, produced and installed more than 5000 meters of guides in many European, American and Asian countries. To reinforce its leadership and presence in neutron research, CILAS acquired the company Grenoble Modular Instruments (GMI), a leading company in high precision mechanics, engineering and manufacturing of spectrometers and scientific equipment for neutron and synchrotron research. (author)

  20. Neutron recognition in the LAND detector for large neutron multiplicity

    Energy Technology Data Exchange (ETDEWEB)

    Pawlowski, P., E-mail: piotr.pawlowski@ifj.edu.pl [Institute of Nuclear Physics, PAN, Radzikowskiego 152, 31-342 Krakow (Poland); Brzychczyk, J. [Institute of Physics, Jagiellonian University, Reymonta 4, 30-059 Krakow (Poland); Leifels, Y.; Trautmann, W. [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, D-64291 Darmstadt (Germany); Adrich, P. [National Centre for Nuclear Research, PL-00681 Warsaw (Poland); GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, D-64291 Darmstadt (Germany); Aumann, T. [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, D-64291 Darmstadt (Germany); Bacri, C.O. [Institut de Physique Nucleaire, IN2P3-CNRS et Universite, F-91406 Orsay (France); Barczyk, T. [Institute of Physics, Jagiellonian University, Reymonta 4, 30-059 Krakow (Poland); Bassini, R. [Istituto di Scienze Fisiche, Universita degli Studi and INFN, I-20133 Milano (Italy); Bianchin, S. [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, D-64291 Darmstadt (Germany); Boiano, C. [Istituto di Scienze Fisiche, Universita degli Studi and INFN, I-20133 Milano (Italy); Boretzky, K. [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, D-64291 Darmstadt (Germany); Boudard, A. [IRFU/SPhN, CEA/Saclay, F-91191 Gif-sur-Yvette (France); Chbihi, A. [GANIL, CEA et IN2P3-CNRS, F-14076 Caen (France); Cibor, J.; Czech, B. [Institute of Nuclear Physics, PAN, Radzikowskiego 152, 31-342 Krakow (Poland); De Napoli, M. [Dipartimento di Fisica e Astronomia-Universita and INFN-CT and LNS, I-95123 Catania (Italy); and others

    2012-12-01

    The performance of the LAND neutron detector is studied. Using an event-mixing technique based on one-neutron data obtained in the S107 experiment at the GSI laboratory, we test the efficiency of various analytic tools used to determine the multiplicity and kinematic properties of detected neutrons. A new algorithm developed recently for recognizing neutron showers from spectator decays in the ALADIN experiment S254 is described in detail. Its performance is assessed in comparison with other methods. The properties of the observed neutron events are used to estimate the detection efficiency of LAND in this experiment.

  1. Miasis cutanea por cordylobia anthropophaga

    Directory of Open Access Journals (Sweden)

    Alkorta Gurrutxaga Miriam

    2001-01-01

    Full Text Available El incremento progresivo en el número de personas que viajan a países tropicales ha hecho que las enfermedades importadas adquieran una relevancia cada vez mayor. Las miasis (o infestaciones por larvas de moscas cutáneas se encuentran entre este tipo de enfermedades siendo especialmente frecuentes en países tropicales. A propósito de la observación de un caso de miasis cutánea masiva por Cordylobia antropophaga, que ocurrió en una mujer de 34 años de edad al volver de un viaje a Senegal, se ha efectuado una revisión de los casos de miasis cutáneas forunculoides importadas publicados en España, así como de la biología, patología, tratamiento y prevención de la miasis humana por Cordylobia anthropophaga. El caso referido, se caracterizó por la infestación con un número inusualmente elevado de larvas, no sospechándose su etiología hasta la fase final de la enfermedad. La emergencia continuada de larvas (se recogieron 91 generó en la paciente un estado de ansiedad importante. Finalmente, la eliminación de las larvas provocó una rápida mejoría de la paciente. Aunque los casos de miasis cutánea no tienen la gravedad de otras enfermedades importadas, su conocimiento es necesario desde el punto de vista preventivo, diagnóstico y terapeútico. Es importante proceder a la identificación morfológica de las larvas diferenciándolas de otro tipo de miasis con implicaciones terapéuticas diferentes.

  2. Tratamiento del Cáncer con captura de Neutrones

    Directory of Open Access Journals (Sweden)

    Jaime Gómez Gonzalez

    1997-12-01

    Full Text Available

    La captura de átomos de boro, gadolinio o la mezcla de estos dos elementos para tratamiento del cáncer es un método experimental que está demostrando gran utilidad en el tratamiento de los tumores cerebrales malignos y de melanomas. Se espera que en un futuro próximo se pueda utilizar en la terapia del cáncer del pulmón, próstata y seno.

    La captura de átomos de boro con neutrones es un método bifásico: Requiere la inyección de una substancia con afinidad por el tejido neoplásico como el boro o el gadolinio y la exposición del enfermo a un haz de neutrones epitérmicos. Al entrar en contacto los neutrones con el boro o gadolinio captado por las células tumorales, se forma una reacción de fisión limitada a un radio de 5 a 10 micras la cual libera una gran cantidad de energía, produce la destrucción de las trenzas de DNA y del tejido tumoral. Las células normales que no captan boro o gadolinio permanecen indemnes.

    Antecedentes


    El método conocido por la sigla inglesa BNCT (Boron Neutron Capture Therapy fue iniciado en Bastan en los años cincuenta por el DI. William Sweet, profesor de neurocirugía de la Universidad de Harvard. Entre 1950 y 1960 se trataron cerca de 50 enfermos con tumores cerebrales malignos. Los resultados no fueron satisfactorios porque el compuesto borado y los neutrones que se utilizaron fueron de baja energía.

    En 1964 Hiroshi Hatanaka, un neurocirujano japonés, trabajó con el DI. Sweet y aprendió el método. A su regreso a Japón en 1967 modificó el sistema con la introducción de un compuesto borado de segunda generación conocido como BSH (borocaptato de sodio. Hatanaka utilizaba la técnica de craneotomía abierta bajo anestesia general y exposición a los neutrones térmicos.

    En 1993 Hatanaka presentó en el Congreso Mundial de Neurocirugía reunido en Acapu1co, México, los resultados de veinticinco años de trabajo y mostr

  3. Neutronic analysis of JET external neutron monitor response

    Energy Technology Data Exchange (ETDEWEB)

    Snoj, Luka, E-mail: luka.snoj@ijs.si [Reactor Physics Division, Jožef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana (Slovenia); Lengar, Igor; Čufar, Aljaž [Reactor Physics Division, Jožef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana (Slovenia); Syme, Brian; Popovichev, Sergey [Culham Centre for Fusion Energy, Culham Science Centre, Abingdon, OX14 3DB, United Kingdom (United Kingdom); Batistoni, Paola [ENEA C. R. Frascati, via E. Fermi 45, 00044 Frascati, Roma (Italy); Conroy, Sean [VR Association, Uppsala University, Department of Physics and Astronomy, PO Box 516, SE-75120 Uppsala (Sweden)

    2016-11-01

    Highlights: • We model JET tokamak containing JET remote handling system. • We investigate effect of remote handling system on external neutron monitor response. • Remote handling system correction factors are calculated. • Integral correction factors are relatively small, i.e up to 8%. - Abstract: The power output of fusion devices is measured in terms of the neutron yield which relates directly to the fusion yield. JET made a transition from Carbon wall to ITER-Like Wall (Beryllium/Tungsten/Carbon) during 2010–11. Absolutely calibrated measurement of the neutron yield by JET neutron monitors was ensured by direct measurements using a calibrated {sup 252}Cf neutron source (NS) deployed by the in-vessel remote handling system (RHS) inside the JET vacuum vessel. Neutronic calculations were required in order to understand the neutron transport from the source in the vacuum vessel to the fission chamber detectors mounted outside the vessel on the transformer limbs of the tokamak. We developed a simplified computational model of JET and the JET RHS in Monte Carlo neutron transport code MCNP and analyzed the paths and structures through which neutrons reach the detectors and the effect of the JET RHS on the neutron monitor response. In addition we performed several sensitivity studies of the effect of substantial massive structures blocking the ports on the external neutron monitor response. As the simplified model provided a qualitative picture of the process only, some calculations were repeated using a more detailed full 3D model of the JET tokamak.

  4. Sequia inminente de neutrones en Europa Cuatro regiones aspiran a la nueva fuente europea de espalacion, pendiente de una decision politica

    CERN Multimedia

    Elvira, M

    2002-01-01

    "Faltan neutrones. Dicho asi, puede parecer extrano, pero es cierto. Los cientificos e ingenieros no tienen suficientes neutrones para observar la materia a nivel microscopico como les gustaria. Se asoman a posibilidades que les seducen pero no pueden ir mas alla por falta de una cantidad suficiente de estas particulas, que deben ser generadas en reactores o aceleradores " (2 pages).

  5. Particle physics with cold neutrons

    International Nuclear Information System (INIS)

    Dubbers, D.

    1991-01-01

    Slow neutrons are used in a large number of experiments to study the physics of particles and their fundamental interactions. Some of these experiments search for manifestations of ''new physics'' like baryon- or lepton-number nonconservation, time reversal nonconservation, new particles, right-handed currents, nonzero neutron charge, nonlinear terms in the Schrodinger equation, exotic e + e - states, and others. Other slow neutron experiments test the present Standard Model. The parity nonconserving weak neutron-nucleon interaction is studied in a variety of experiments. Free neutron beta decay gives precise values for the weak vector and axialvector coupling constants, which allow precise tests of basic symmetries like the conservation of the weak vector current, the unitarity of the weak quark mixing matrix, SU(3) flavour symmetry, and right-handed currents. Neutron beta decay data are further needed to calculate weak cross-sections, for applications, in big bang cosmology, in astrophysics, in solar physics and the solar neutrino problem, and in such mundane things as neutrino detection efficiencies in neutrino oscillation or proton decay experiments. Neutron-nucleon, neutron-nucleus and neutron-electron scattering lengths are determined in high precision experiments, which use methods like neutron interferometry or neutron gravity spectrometry. The experiments give information on quantities like the neutron charge radius or the neutron electric polarizability. Precision measurements of other fundamental constants lead to a better, model-independent value of the fine structure constant. Finally, the fundamental experiments on quantum mechanics, like spinor 4π -rotation, Berry's phase, dressed neutrons, Aharanov - Casher effect, or gravitational effects on the neutron's phase will be briefly discussed. (author)

  6. Abdome agudo por obstrução por ileobiliar

    Directory of Open Access Journals (Sweden)

    Márcia Cristina de Alencastro

    Full Text Available OBJETIVO: descrever a experiência na abordagem dos doentes com abdome agudo por obstrução por IB, desde o diagnóstico até o tratamento definitivo. MÉTODOS: estudo retrospectivo incluindo todos os casos de IB tratados em um período de 23 anos. De acordo com a abordagem cirúrgica realizada, os pacientes foram divididos em dois grupos (1 enterolitotomia com colecistectomia no segundo momento; e (2 enterolitotomia, colecistectomia e abordagem da fístula. RESULTADOS: Doze pacientes foram incluídos, sendo 11 mulheres (91,6%, com média de idade de 72,2 anos. Todos os pacientes apresentavam doenças associadas, principalmente hipertensão arterial sistêmica (75%. Dois pacientes não apresentavam sintomas significativos de obstrução intestinal. O diagnóstico de IB foi realizado em seis pacientes (50% antes da laparotomia. O grupo 1 foi constituído de oito pacientes e o grupo 2 de quatro, e a morbidade foi, respectivamente, 33,3% e 8,3%. A mortalidade foi 16,6% (um paciente de cada grupo. CONCLUSÃO: O manejo do IB deve ser individualizado. O tratamento da obstrução mediante remoção do cálculo biliar por enterotomia proximal é a escolha inicial para o tratamento do IB. A colecistectomia e a correção da fístula bilioentérica podem ser realizadas juntamente com a remoção do cálculo, no entanto, em pacientes com comorbidades significativas, esses procedimentos devem ser realizados posteriormente.

  7. The tokamak as a neutron source

    International Nuclear Information System (INIS)

    Hendel, H.W.; Jassby, D.L.

    1989-11-01

    This paper describes the tokamak in its role as a neutron source, with emphasis on experimental results for D-D neutron production. The sections summarize tokamak operation, sources of fusion and non-fusion neutrons, principal neutron detection methods and their calibration, neutron energy spectra and fluxes outside the tokamak plasma chamber, history of neutron production in tokamaks, neutron emission and fusion power gain from JET and TFTR (the largest present-day tokamaks), and D-T neutron production from burnup of D-D tritons. This paper also discusses the prospects for future tokamak neutron production and potential applications of tokamak neutron sources. 100 refs., 16 figs., 4 tabs

  8. The Los Alamos Neutron Science Center Spallation Neutron Sources

    International Nuclear Information System (INIS)

    Nowicki, Suzanne F.; Wender, Stephen A.; Mocko, Michael

    2017-01-01

    The Los Alamos Neutron Science Center (LANSCE) provides the scientific community with intense sources of neutrons, which can be used to perform experiments supporting civilian and national security research. These measurements include nuclear physics experiments for the defense program, basic science, and the radiation effect programs. This paper focuses on the radiation effects program, which involves mostly accelerated testing of semiconductor parts. When cosmic rays strike the earth's atmosphere, they cause nuclear reactions with elements in the air and produce a wide range of energetic particles. Because neutrons are uncharged, they can reach aircraft altitudes and sea level. These neutrons are thought to be the most important threat to semiconductor devices and integrated circuits. The best way to determine the failure rate due to these neutrons is to measure the failure rate in a neutron source that has the same spectrum as those produced by cosmic rays. Los Alamos has a high-energy and a low-energy neutron source for semiconductor testing. Both are driven by the 800-MeV proton beam from the LANSCE accelerator. The high-energy neutron source at the Weapons Neutron Research (WNR) facility uses a bare target that is designed to produce fast neutrons with energies from 100 keV to almost 800 MeV. The measured neutron energy distribution from WNR is very similar to that of the cosmic-ray-induced neutrons in the atmosphere. However, the flux provided at the WNR facility is typically 5×107 times more intense than the flux of the cosmic-ray-induced neutrons. This intense neutron flux allows testing at greatly accelerated rates. An irradiation test of less than an hour is equivalent to many years of neutron exposure due to cosmic-ray neutrons. The low-energy neutron source is located at the Lujan Neutron Scattering Center. It is based on a moderated source that provides useful neutrons from subthermal energies to ~100 keV. The characteristics of these sources

  9. The Los Alamos Neutron Science Center Spallation Neutron Sources

    Science.gov (United States)

    Nowicki, Suzanne F.; Wender, Stephen A.; Mocko, Michael

    The Los Alamos Neutron Science Center (LANSCE) provides the scientific community with intense sources of neutrons, which can be used to perform experiments supporting civilian and national security research. These measurements include nuclear physics experiments for the defense program, basic science, and the radiation effect programs. This paper focuses on the radiation effects program, which involves mostly accelerated testing of semiconductor parts. When cosmic rays strike the earth's atmosphere, they cause nuclear reactions with elements in the air and produce a wide range of energetic particles. Because neutrons are uncharged, they can reach aircraft altitudes and sea level. These neutrons are thought to be the most important threat to semiconductor devices and integrated circuits. The best way to determine the failure rate due to these neutrons is to measure the failure rate in a neutron source that has the same spectrum as those produced by cosmic rays. Los Alamos has a high-energy and a low-energy neutron source for semiconductor testing. Both are driven by the 800-MeV proton beam from the LANSCE accelerator. The high-energy neutron source at the Weapons Neutron Research (WNR) facility uses a bare target that is designed to produce fast neutrons with energies from 100 keV to almost 800 MeV. The measured neutron energy distribution from WNR is very similar to that of the cosmic-ray-induced neutrons in the atmosphere. However, the flux provided at the WNR facility is typically 5×107 times more intense than the flux of the cosmic-ray-induced neutrons. This intense neutron flux allows testing at greatly accelerated rates. An irradiation test of less than an hour is equivalent to many years of neutron exposure due to cosmic-ray neutrons. The low-energy neutron source is located at the Lujan Neutron Scattering Center. It is based on a moderated source that provides useful neutrons from subthermal energies to ∼100 keV. The characteristics of these sources, and

  10. Optical neutron polarizers

    International Nuclear Information System (INIS)

    Hayter, J.B.

    1990-01-01

    A neutron wave will be refracted by an appropriately varying potential. Optical neutron polarizers use spatially varying, spin- dependent potentials to refract neutrons of opposite spin states into different directions, so that an unpolarized beam will be split into two beams of complementary polarization by such a device. This paper will concentrate on two methods of producing spin-dependent potentials which are particularly well-suited to polarizing cold neutron beams, namely thin-film structures and field-gradient techniques. Thin-film optical devices, such as supermirror multilayer structures, are usually designed to deviate only one spin-state, so that they offer the possibility of making insertion (transmission) polarizers. Very good supermirrors may now be designed and fabricated, but it is not always straightforward to design mirror-based devices which are useful in real (divergent beam) applications, and some practical configurations will be discussed. Field-gradient devices, which are usually based on multipolar magnets, have tended to be too expensive for general use, but this may change with new developments in superconductivity. Dipolar and hexapolar configurations will be considered, with emphasis on the focusing characteristics of the latter. 21 refs., 7 figs

  11. Neutron-proton scattering

    International Nuclear Information System (INIS)

    Doll, P.

    1990-02-01

    Neutron-proton scattering as fundamental interaction process below and above hundred MeV is discussed. Quark model inspired interactions and phenomenological potential models are described. The seminar also indicates the experimental improvements for achieving new precise scattering data. Concluding remarks indicate the relevance of nucleon-nucleon scattering results to finite nuclei. (orig.) [de

  12. Neutron resonance absorption theory

    International Nuclear Information System (INIS)

    Reuss, P.

    1991-11-01

    After some recalls on the physics of neutron resonance absorption during their slowing down, this paper presents the main features of the theoretical developments performed by the french school of reactor physics: the effective reaction rate method so called Livolant-Jeanpierre theory, the generalizations carried out by the author, and the probability table method [fr

  13. Neutron protein crystallography

    Energy Technology Data Exchange (ETDEWEB)

    Niimura, Nobuo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-10-01

    X-ray diffraction of single crystal has enriched the knowledge of various biological molecules such as proteins, DNA, t-RNA, viruses, etc. It is difficult to make structural analysis of hydrogen atoms in a protein using X-ray crystallography, whereas neutron diffraction seems usable to directly determine the location of those hydrogen atoms. Here, neutron diffraction method was applied to structural analysis of hen egg-white lysozyme. Since the crystal size of a protein to analyze is generally small (5 mm{sup 3} at most), the neutron beam at the sample position in monochromator system was set to less than 5 x 5 mm{sup 2} and beam divergence to 0.4 degree or less. Neutron imaging plate with {sup 6}Li or Gd mixed with photostimulated luminescence material was used and about 2500 Bragg reflections were recorded in one crystal setting. A total of 38278 reflections for 2.0 A resolution were collected in less than 10 days. Thus, stereo views of Trp-111 omit map around the indol ring of Trp-111 was presented and the three-dimensional arrangement of 696H and 264D atoms in the lysozyme molecules was determined using the omit map. (M.N.)

  14. Neutron rich nuclei

    International Nuclear Information System (INIS)

    Foucher, R.

    1979-01-01

    If some β - emitters are particularly interesting to study in light, medium, and heavy nuclei, another (and also) difficult problem is to know systematically the properties of these neutron rich nuclei far from the stability line. A review of some of their characteristics is presented. How far is it possible to be objective in the interpretation of data is questioned and implications are discussed

  15. Applied neutron resonance theory

    International Nuclear Information System (INIS)

    Froehner, F.H.

    1980-01-01

    Utilisation of resonance theory in basic and applications-oriented neutron cross section work is reviewed. The technically important resonance formalisms, principal concepts and methods as well as representative computer programs for resonance parameter extraction from measured data, evaluation of resonance data, calculation of Doppler-broadened cross sections and estimation of level-statistical quantities from resonance parameters are described. (author)

  16. Interferometry with polarised neutrons

    International Nuclear Information System (INIS)

    Badurek, G.

    1978-01-01

    This paper aimed to give an outline of what might be expected from an extension of polarized beam techniques in neutron interferometry and how it could be achieved properly and what is the present state of this special field of interferometry

  17. Self powered neutron detectors

    International Nuclear Information System (INIS)

    Gopalan, C.S.; Ramachandra Rao, M.N.; Ingale, A.D.

    1976-01-01

    Two types of self powered neutron detectors used for in-core flux measurements are described. The characteristics of the various detectors, with emitters Rh, V, Co, Py are presented. Details about the fabrication of these detectors are given. (A.K.)

  18. New Neutron Dosimeter

    CERN Multimedia

    2001-01-01

    CERN has been operating an Individual Dosimetry Service for neutrons for about 35 years. The service was based on nuclear emulsions in the form of film packages which were developed and scanned in the Service. In 1999, the supplier of theses packages informed CERN that they will discontinue production of this material. TIS-RP decided to look for an external service provider for individual neutron dosimetry. After an extensive market survey and an invitation for tender, a supplier that met the stringent technical requirements set up by CERN's host states for personal dosimeters was identified. The new dosimeter is based on a track-etching technique. Neutrons have the capability of damaging plastic material. The microscopic damage centres are revealed by etching them in a strong acid. The resulting etch pits can be automatically counted and their density is proportional to dose equivalent from neutrons. On the technical side, the new dosimeter provides an improved independence of its response from energy and th...

  19. NEUTRONIC REACTOR STRUCTURE

    Science.gov (United States)

    Weinberg, A.M.; Vernon, H.C.

    1961-05-30

    A neutronic reactor is described. It has a core consisting of natural uranium and heavy water and having a K-factor greater than unity which is surrounded by a reflector consisting of natural uranium and ordinary water having a Kfactor less than unity.

  20. Neutron metrology for SBSS

    International Nuclear Information System (INIS)

    Morris, C.L.; Anaya, J.M.; Armijo, V.

    1998-01-01

    This is the final report of a two-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). The goal of this work is to develop new detector technologies for Science-Based Stockpile Stewardship (SBSS) at the Los Alamos Neutron Scattering Center (LANSCE) using existing expertise and infrastructure from the nuclear and particle physics programs at LANL