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Garcia Garcia, Florencio.
Chile Univ., Santiago. Dept. de Electridad1979
Chile Univ., Santiago. Dept. de Electridad1979
AbstractAbstract
[en] Self powered neutron detectors are becoming more and more popular in reactor instrumentation. A fast response detector of this type was made at the Reactor Division, La Reina Nuclear Center in Santiago. Cobalt wire was the emitter, teflon the insulator and a stainless steel tubing was the collector. The overall dimensions of the detector are 6 mms diameter and 700 mms length. The irradiation tests, carried out at the Center's 5 Mw research reactor showed a very reasonably linear relation between current supplied by the detector and thermal neutron flux, over a range extending from 1010 to 1013 n/cm2 x seg. These tests also showed a good agreement between calculated and measured current. The models used for the calculation of current are fully explained and they include some improvements over those that have been published recently. An important conclusion for the case of the cobalt detectors is that the wire's diameter must be at least 1 mm. in order to have a neutron induced current bigger than the parasitic components generated by indirect processes. Calculations for other emitters such as vanadium, silver and rhodum are also included. (EC)
Original Title
Diseno y construccion de un detector de neutrones autoalimentado
Source
1979; 149 p; Available from Comision Chilena de Energia Nuclear, Santiago (Chile); Thesis.
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Miscellaneous
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Thesis/Dissertation
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Banados Perez, H.E.
Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)1990
Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)1990
AbstractAbstract
[en] Published in summary form only
Original Title
Situacao atual do desenvolvimento de detectores de neutrons para instrumentacao de reatores nucleares no IPEN -CNEN/SP
Primary Subject
Source
1990; 1 p
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Miscellaneous
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AbstractAbstract
[en] A commercial bubble damage polymer detector for neutrons has been produced. The energy threshold is 100 keV and the dose equivalent response is ± 20% between 200 keV and 14 MeV, with a sensitivity of 1 to 5 bubbles per mrem. A reusable detector is available which can be recycled daily or weekly for up to three months. A neutron spectrometer kit has six bubble detectors with energy thresholds of 10 keV, 100 keV, 500 keV, 1 MeV, 3 MeV and 10 MeV. A gamma bubble detector has also been developed. (author)
Source
14. international conference on solid state nuclear track detectors; Lahore (Pakistan); 2-6 Apr 1988
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Journal Article
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Feller, W. Bruce
NOVA Scientific, Inc. Sturbridge, MA (United States). Funding organisation: USDOE Office of Science (United States)2008
NOVA Scientific, Inc. Sturbridge, MA (United States). Funding organisation: USDOE Office of Science (United States)2008
AbstractAbstract
[en] The neutron detector that was contracted by NIST on behalf of Office of Science for ORNL has been delivered to ORNL. The attached letter from Ron Cooper supports the acceptance of the deliverable.
Primary Subject
Source
1 Aug 2008; 40 MB; SB1341-06-C-0026; AI02-06ER12271; Available from OSTI as DE00952486; PURL: https://www.osti.gov/servlets/purl/952486-dp20Bn/; doi 10.2172/952486
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Menlove, Howard Olsen; Henzlova, Daniela
Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Funding organisation: USDOE National Nuclear Security Administration (NNSA). Office of Defense Nuclear Nonproliferation (NA-20) (United States)2017
Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Funding organisation: USDOE National Nuclear Security Administration (NNSA). Office of Defense Nuclear Nonproliferation (NA-20) (United States)2017
AbstractAbstract
No abstract available
Primary Subject
Source
9 Aug 2017; 19 p; OSTIID--1375134; AC52-06NA25396; Available from http://permalink.lanl.gov/object/tr?what=info:lanl-repo/lareport/LA-UR-17-27159; PURL: http://www.osti.gov/servlets/purl/1375134/
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AbstractAbstract
[en] The radiation detector for neutrons, for example, consists of a radiation-sensitive and a radiation-insensitive temperature compensated semiconductor diode in a bridge circuit. Both diodes are integrated in a common germanium or silicon semiconductor solid state device. The radiation-sensitive semiconductor diode is formed by diffusion of a p+ zone; the pn transition of the radiation-insensitive one is also formed by diffusion of a p+ zone. The diffusion takes place through a diffusion window in a silicon dioxide nitride layer on the planar diodes. The radiation insensitivity of one diode is produced by recombination centre formation from gold or copper, which are also diffused. For full integration of the bridge circuit, the ohmic resistances can be evaporated on to the semiconductors as oxide layers. (DG) 891 HP
[de]
Strahlungsdetektor fuer z.B. Neutronen, besteht aus einer strahlungsempfindlichen und einer strahlungsunempfindlichen, temperaturkompensierenden Halbleiterdiode in einer Brueckenschaltung. Beide Dioden sind in einem gemeinsamen Halbleiterkoerper (Ge oder S ) integriert. Die strahlungsempfindliche Halbleiterdiode entsteht durch die Eindiffusion einer p+ -Zone; der pn-Uebergang der strahlenunempfindlichen durch Eindiffundieren auch einer p+ -Zone. Die Eindiffusion erfolgt durch Diffusionsfenster in einer Silidioxid -od. nitridschicht auf den Planardioden. Die Strahlenunempfindlichkeit der einen Diode wird durch Rekombinationszentrenbildner aus Au oder Cu erzeugt, die ebenfalls eindiffundiert wurden. Zur Vollintegration der Brueckenschaltung koennen die ohm'schen Widerstaende als Oxidschichten auf den Halbleiterkoerper aufgedampft werden. (DG)Original Title
Strahlungsdosimeter mit Halbleiterdioden als Strahlungsindikator und zur Temperaturkompensation
Secondary Subject
Source
8 Dec 1977; 4 p; DE PATENT DOCUMENT 1614764/B/
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Patent
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Prokhorets, I.M.; Prokhorets, S.I.; Skrypnik, A.I.; Khazhmuradov, M.A.
Book of abstracts of the 9th Conference on High Energy Physics, Nuclear Physics and Accelerators2011
Book of abstracts of the 9th Conference on High Energy Physics, Nuclear Physics and Accelerators2011
AbstractAbstract
No abstract available
Original Title
Detektory nejtronov dlya reaktornoj dozimetrii
Primary Subject
Source
Natsional'naya Akademiya Nauk Ukrainy, Kyiv (Ukraine); Natsional'nyj Nauchnyj Tsentr Khar'kovskij Fiziko-Tekhnicheskij Institut , Khar'kov (Ukraine); Institut Fiziki Vysokikh Ehnergij i Yadernoj Fiziki, Khar'kov (Ukraine); 120 p; 2011; p. 95; 9. Conference on High Energy Physics, Nuclear Physics and Accelerators; Tezisy dokladov 9-j konferentsii po fizike vysokikh ehnergij, yadernoj fizike i uskoritelyam; Kharkov (Ukraine); 21-25 Feb 2011; Available from Ukrainian INIS Centre
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Related RecordRelated Record
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AbstractAbstract
[en] The methods used in radiation reactor dosimetry which do not depend on fission reaction nor foil activation are reviewed. These other techniques are especially the following: the different types of self-powered detectors, with fast or slow response, their characteristics of noise and temperature effect, their practical uses; the damage detectors, considering the variations of their physical properties (resistivity, density, ...), and their use for characterizing the neutron spectra; the little loops circulating fluids as, air, nitrogen, helium, water
Original Title
Methodes speciales utilisees en dosimetrie des neutrons
Source
Commission of the European Communities, Petten (Netherlands). Joint Nuclear Research Center; p. 536-549; 1977; p. 536-549; 1. International symposium on reactor dosimetry: developments and standardization; Petten, Netherlands; 22 - 26 Sep 1975
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AbstractAbstract
[en] The paper describes the foil activation detector and the thermoluminescent detector as passive neutron detectors. Also the thermoluminescent dosimeter is discussed for (n-γ) radiations.(author)
Original Title
Detectoare pasive si dozimetre de neutroni
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Journal Article
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Rakel, D.A.
Monsanto Research Corp., Miamisburg, OH (USA). Mound1986
Monsanto Research Corp., Miamisburg, OH (USA). Mound1986
AbstractAbstract
[en] The use of transportable calorimetric assay equipment to perform an in-field calibration of a neutron correlation counter is presented. During the past three years, this combination of instrumentation has been used to measure the plutonium content of a variety of oxide, salt, and metal samples. An increase in sample throughput has been achieved by using this combination of measurements
Primary Subject
Source
1986; 18 p; International symposium on nuclear material safeguards; Vienna (Austria); 10-14 Nov 1986; IAEA-SM--293/126; CONF-861104--12; Available from NTIS, PC A02/MF A01 as DE87003023
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