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AbstractAbstract
[en] An inverse kinetics algorithm applicable to the plutonium-fuelled zero-energy fast reactor PURNIMA has been developed for the interpretation of kinetic experiments. By introducing reactivity perturbation of various kinds and analysing the resultant neutronic behaviour, the worths of various reactivity manipulation mechanisms of PURNIMA reactor have been determined. The technique has proven to be a reliable method for determining the inherent neutron source strenght in the reactor. (orig.)
[de]
Zur Interpretation kinetischer Experimente wurde ein inverskinetischer Algorithmus entwicklet, der fuer den mit Plutonium beschickten schnellen Null-Energie-Reaktor PURNIMA verwendbar ist. Reaktivitaetsaenderungen verschiedener Art wurden angenommen und das resultierende Neutronenverhalten analysiert. Die Reaktivitaetswerte verschiedener Steuerungsmechanismen des PURNIMA-Reaktors wurden so bestimmt. Diese Methode eignet sich zur Bestimmung der reaktoreigenen Neutronenquellstaerke. (orig.)Primary Subject
Source
8 figs.; 1 tab.; 19 refs.
Record Type
Journal Article
Journal
Atomkernenergie; v. 27(1); p. 18-22
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AbstractAbstract
[en] The precise estimation of Pearson correlations, also called 'representativity' coefficients, between core configurations is a fundamental quantity for properly assessing the nuclear data (ND) uncertainties propagation on integral parameters such as k-eff, power distributions, or reactivity coefficients. In this paper, a traditional adjoint method is used to propagate ND uncertainty on reactivity and reactivity coefficients and estimate correlations between different states of the core. We show that neglecting those correlations induces a loss of information in the final uncertainty. We also show that using approximate values of Pearson does not lead to an important error of the model. This calculation is made for reactivity at the beginning of life and can be extended to other parameters during depletion calculations. (authors)
Primary Subject
Source
Available from doi: http://dx.doi.org/10.1051/epjn/2016039; 16 refs.
Record Type
Journal Article
Journal
EPJ Nuclear Sciences and Technologies; ISSN 2491-9292;
; v. 3; p. 6.1-6.9

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AbstractAbstract
No abstract available
Primary Subject
Source
Annual meeting of the American Nuclear Society; Philadelphia, PA; 23 Jun 1974; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Trans. Amer. Nucl. Soc; v. 18 p. 343-344
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AbstractAbstract
[en] The subject is covered under the following headings: (1) introduction, (2) design of WWER type reactors, (3) reactor physics calculations, (4) theoretical fundamentals for determining reactivity effects by reactivity measurements, (5) reactivity measurements and evaluation methods, (6) operating parameters, and (7) transferability of the methods and outlook. 56 references are included
Original Title
Physikalische Experimente an Leistungsreaktoren
Primary Subject
Source
1982; 271 p; Akademie Verlag; Berlin; 56 refs.
Record Type
Book
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AbstractAbstract
[en] Three methods for measuring the reactivity of a system in sub-critical state in the presence of a neutron source are described, namely the method of ''shooting source'', the method of dumping of unknown absorber, and the method of introducing the calibrated absorber. The described methods do not require additional equipment, except for an analogue reactometer with a possibility of adjusting the source component in the computing block. The methods are universal since they cover not only the critical assemblies but also any high-intensity reactors in sub-critical stage and permit the temperature effect, the poisoning effects, etc. to be measured. Besides that, the methods may be applied both in the absence and in the presence of a strong neutron background in the reactor
Original Title
Kontrol' reaktivnosti gluboko podkriticheskikh reaktorov s pomoshch'yu reaktimetrov i korrektirovka analoga istochnika
Primary Subject
Source
5 refs.; for English translation see the journal Sov. At. Energy.
Record Type
Journal Article
Journal
Atomnaya Ehnergiya; v. 41(4); p. 238-241
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Baranyai, A.; Zsido, J.
Hungarian Academy of Sciences, Budapest. Central Research Inst. for Physics
Hungarian Academy of Sciences, Budapest. Central Research Inst. for Physics
AbstractAbstract
[en] The accuracy of reactivity meters is usually checked with a reactor kinetic simulator operating to an accuracy exceeding the expected accuracy of the measuring device. The present report describes a method to evaluate accuracy by comparing the response R(t) of the reactivity meter to a given function n(t) with the value of the reactivity function r(t) calculated from the same input function instead of using the input reference signal r(t) to the simulator with the output signal R(t) from the reactivity meter. This method has been successfully used by applying sawtooth and exponential input signals for the determination of the accuracy of reactivity meters developed in the Central Research Institute for Physics. (author)
Primary Subject
Secondary Subject
Source
Feb 1983; 10 p; ISBN 963 372 040 0;
; 8 refs.

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Report
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AbstractAbstract
[en] The results of calculations of various models of the BN-600 reactor using the method developed earlier to calculate the contribution of neutron-capture reactions to the effective energy release in the nuclear reactor core are presented in the paper. Three models of the BN-600 reactor have been calculated: a cell model, a blanket cell and a homogeneous core (with uranium, MOX, and hybrid fuels)
[ru]
В данной работе приведены результаты расчетов различных моделей реактора БН-600 с использованием разработанной ранее методики для расчета вклада нейтронно-захватных реакций в эффективное энерговыделение в активной зоне ядерного реактора. Были рассчитаны три модели реактора БН-600: модель ячейки, ячейки с бланкетом и гомогенной активной зоны (с урановым, МОХ и гибридным топливом)Original Title
Vklad nejtronno-zakhvatnykh reaktsij v ehnergovydelenie v aktivnoj zone bystrogo reaktora
Primary Subject
Source
Available online: https://vant.ippe.ru/en/; 19 refs., 3 figs., 7 tabs.
Record Type
Journal Article
Journal
Voprosy Atomnoj Nauki i Tekhniki. Seriya: Yaderno-Reaktornye Konstanty; ISSN 2414-1038;
; (no.1); p. 87-97

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AbstractAbstract
[en] A method for at-power reactivity measurements is presented. The method is based on a trapezoidal perturbation of the reactor state, which can be generated easily by means of ordinary control rods. Both theoretical and experimental work are discussed, and a simple algorithm for the correction of space-time effects is suggested
Primary Subject
Record Type
Journal Article
Journal
Nuclear Science and Engineering; ISSN 0029-5639;
; v. 71(3); p. 309-318

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Ronen, Y.; Schneider, A.
Israel Atomic Energy Commission, Beersheba. Nuclear Research Center-Negev
Israel Atomic Energy Commission, Beersheba. Nuclear Research Center-Negev
AbstractAbstract
No abstract available
Primary Subject
Source
May 1974; 16 p; 4 refs.; fig.; appendix.
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Report
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AbstractAbstract
[en] Nowadays, various digital methods making use of microcomputers for neutron detector signals and determining the reactivity by numerical calculations are used in reactor control systems in place of classical reactivity meters. In this work, a calculation based on the ''The Time Dependent Transport Equation'' has been developed for determining the reactivity numerically. The reactivity values have been obtained utilizing a computer-based data acquisition and control system and compared with the analog reactivity meter values as well as the values calculated from the ''Inhour Equation''
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Journal Article
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