[en] The report is devoted to the 55-year experience in operation of the first Soviet nuclear reactor F-1, started-up on December 25, 1946. The material science, physical, reactor and medicinal studies, accomplished at this reactor, are enumerated. Various studies are continued presently at the F-1 reactor. It has the license of the Gosatomnadzor for operation and is certified as the calibration standard for the neutron flux density
[ru]
Доклад посвящен опыту 55-летней эксплуатации первого советского ядерного реактора Ф-1, запущенного 25 декабря 1946 г. Перечисляются материаловедческие, физические, реакторные и медицинские исследования, выполненные на этом реакторе. В настоящее время на реакторе Ф-1 продолжаются различные исследования. Он имеет лицензию Госатомнадзора на эксплуатацию и аттестован как рабочий эталон плотности потока нейтроновSource
Klinov, A.V. (comp.); Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Yadernoe Obshchestvo Rossii, Moscow (Russian Federation); Federal'noe Gosudarstvennoe Unitarnoe Predpriyatie Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii - Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (Russian Federation); 288 p; ISBN 5-94831-003-5; 
; 2002; p. 71-80; 12. Annual conference of the Nuclear Society of Russia. Research reactors: science and high technologies; XII ezhegodnaya konferentsiya Yadernogo Obshchestva Rossii. Issledovatel'skie reaktory: nauka i vysokie tekhnologii; Dimitrovgrad (Russian Federation); 25-29 Jun 2001; 8 refs., 2 figs., 2 tabs.
; 2002; p. 71-80; 12. Annual conference of the Nuclear Society of Russia. Research reactors: science and high technologies; XII ezhegodnaya konferentsiya Yadernogo Obshchestva Rossii. Issledovatel'skie reaktory: nauka i vysokie tekhnologii; Dimitrovgrad (Russian Federation); 25-29 Jun 2001; 8 refs., 2 figs., 2 tabs.
[en] The strategy of the neutron activation analysis using the intermediate neutrons in the field of nonoverlapping neutron resonances was developed. The 10B absorber with the 1 cm thickness was used for the isolation of the necessary area of the F-1 reactor neutron spectrum. It is shown that the utilizing this area of the neutron spectrum allows rather uniformly activate the large thickness of any element in spite of resonance type of the capture. At the same time other elements even comprising the basis of the sample are not a barrier in the determination of the desired element content considering that neutron resonances, as a rule, are nonoverlapped
[ru]
Разработана методика нейтронно-активационного анализа с использованием промежуточных нейтронов в области неперекрывающихся нейтронных резонансов. Для выделения необходимой области нейтронного спектра реактора Ф-1 использовали поглотитель из 10B толщиной 1 см. Показано, что использование этой области спектра нейтронов позволяет сравнительно равномерно активировать большую толщину любого элемента, несмотря на резонансный тип захвата. В то же время другие элементы, даже составляющие основу образца, почти не мешают определению содержания искомого элемента, поскольку нейтронные резонансы, как правило, не перекрываютсяJournal
No abstract available
Source
Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Yadernoe Obshchestvo Rossii, Moscow (Russian Federation); Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (Russian Federation); 104 p; ISBN 5-85165-655-7; ; 2001; p. 41-45; 12. Annual conference of the Nuclear Society of Russia. Research reactors: science and high technologies; 12. Ezhegodnaya konferentsiya Yadernogo Obshchestva Rossii. Issledovatel'skie reaktory: nauka i vysokie tekhnologii; Dimitrovgrad (Russian Federation); 25-29 Jun 2001; 2 figs.
; 2001; p. 41-45; 12. Annual conference of the Nuclear Society of Russia. Research reactors: science and high technologies; 12. Ezhegodnaya konferentsiya Yadernogo Obshchestva Rossii. Issledovatel'skie reaktory: nauka i vysokie tekhnologii; Dimitrovgrad (Russian Federation); 25-29 Jun 2001; 2 figs.
[en] Paper presents the results of the calculating and experimental efforts to study the energy spectra of the neutrons of the Kurchatov Institute nuclear power systems varying in the arrangements of the reactor core and of the reflectors. The measurements were based on the application of the resonance activation standardized composition detectors. Paper presents some of the measurement results
[ru]
Представлены результаты расчетно-экспериментальных исследований параметров энергетических спектров нейтронов ядерных установок РНЦ Курчатовский институт, имеющих разные конструкции активных зон, отражателей, параметры и виды топливных элементов. Измерения проводили с использованием методики резонансных активационных унифицированных композиционных детекторов. Представлены отдельные результаты измеренийJournal
[en] Main requirements for reactivity meters for research reactors and critical assemblies are considered. Description of a wide-range reactivity meter and reactivity calculation algorithm are considered. The results of experimental operation of the reactivity meters with subsequent recommendations on their application in control systems of research reactors and critical assemblies are presented
Journal
[en] The space-energy distribution of thermal neutrons has been measured in a two-zone system consisting of a graphite block, 100 x 100 x 59.5 cm, with an adjacent water cylinder of diameter 37 cm. The system studied was set up in the WWR-2 reactor bay close to the core, which served as external neutron source. To obtain the necessary temperature gradient between the zones, the graphite and water were separated by a thin layer of thermal insulation. Measurements were made at era phi te temperatures of 133, 303, 359 and 443°K. At a graphite temperature of 133°K the water temperature was kept at 297 or 343*K, and in the remaining cases the temperature of the water was 294 and 304°K. The low graphite temperature was obtained by cooling the graphite block with liquid nitrogen. The neutron spectra were measured at different distances from the graphite-water boundary using the time-of-flight method. The results of the measurements indicate that there is a pronounced increase in the neutron temperature relaxation length as the graphite temperature decreases. The paper gives experimental results and compares the measured spectra with calculated values obtained by solving the kinetic equation taking account of the anisotropy of neutron inelastic scattering in cold graphite. (author)
[ru]
V dvuhzonnoj sisteme, sostojashhej iz grafitovogo bloka razmerami 100 x 100 x 59,5 sm, i primykajushhego k nemu vodjanogo cilindra diametrom 37 sm izmereno prostranstvenno-jenergeticheskoe raspredelenie teplovyh nejtronov. Issleduemaja sistema raspolagalas' v nishe reaktora BBP-2 vplotnuju k aktivnoj zone, kotoraja sluzhila vneshnim istochnikom nejtronov. Dlja sozdanija neobhodimogo gradienta temperatury mezhdu zonami, grafit i voda byli razdeleny tonkim sloem teploizoljacii. Izmerenija provodilis' pri temperature grafita 133, 303, 359 i 443 °K. Pri temperature grafita 133°K temperatura vody podderzhivalas' ravnoj 297 ili 343°K, v ostal'nyh sluchajah temperatura vody byla ravna 294 i 304°K. Nizkaja temperatura grafita dostigalas' pri ohlazhdenii grafitovogo bloka zhidkim azotom. Spektry nejtronov byli izmereny na razlichnyh rasstojanijah ot granicy grafita s vodoj metodom vremeni proleta. Rezul'taty izmerenij ukazyvajut na sil'noe vozrastanie dliny relaksacii temperatury nejtronov s umen'sheniem temperatury grafita. Predstavleny rezul'taty jeksperimenta i provedeno sravnenie izmerennyh spektrov s raschetami, poluchennymi pri reshenii kineticheskogo uravnenija s uchetom anizotropii uprugogo rassejanija nejtronov v holodnom grafite. (author)Source
International Atomic Energy Agency, Vienna (Austria); 546 p; Feb 1968; p. 233-244; Symposium on Neutron Thermalization and Reactor Spectra; Ann Arbor, MI (United States); 17-21 Jul 1967; IAEA-SM--96/82; ISSN 0074-1884; ; 12 refs., 8 figs.
; 12 refs., 8 figs.