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AbstractAbstract
[en] The aim of this is to derive a reliable neutron spectrum information to be used in further shielding calculation. Consequently, it was intended to improve the quality of these information by emphasizing correct evaluation of the related uncertainty data. In order to meet these objectives, existing methods and procedures for neutron spectrum calculation and measurement were improved. (author)
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Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil); Associacao Brasileira de Energia Nuclear, Rio de Janeiro, RJ (Brazil); 492 p; 1991; p. 443-448; 8. Brazilian Meeting on Reactor Physics and Thermal Hydraulics; Atibaia, SP (Brazil); 17-20 Sep 1991
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AbstractAbstract
No abstract available
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Joint meeting of the American Nuclear Society; Miami Beach, Fla; 17 Oct 1971
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Journal Article
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Trans. Amer. Nucl. Soc; v. 14(2); p. 836-837
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Knapp, P. F.; Schmit, P. F.; Hansen, S. B.; Gomez, M. R.; Hahn, K. D.; Sinars, D. B.; Peterson, K. J.; Slutz, S. A.; Sefkow, A. B.; Awe, T. J.; Harding, E.; Jennings, C. A.; Desjarlais, M. P.; Chandler, G. A.; Cooper, G. W.; Cuneo, M. E.; Geissel, M.; Harvey-Thompson, A. J.; Porter, J. L.; Rochau, G. A.2015
AbstractAbstract
No abstract available
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(c) 2015 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA)
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Ivanov, B.I.; Rosek, J.
Joint Inst. for Nuclear Research, Dubna (Russian Federation). Lab. of Nuclear Problems1991
Joint Inst. for Nuclear Research, Dubna (Russian Federation). Lab. of Nuclear Problems1991
AbstractAbstract
[en] The program ANS which is the graphical user friendly program to process evaluated neutron data files for interpretation of transmission experiments. The ANS program was written in the Turbo Pascal v. 5 language and may work on the IBM AT with Math CoProcessor. 3 refs.; 1 fig
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1991; 10 p
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AbstractAbstract
[en] The calculated sensitivity coefficients show that in a hybrid reactor the greatest influence on the principal functionals is exerted by the secondary neutron spectra of the reactions 238U(n, 2n), 23BU(n, n/prime/) cont, and Fe(n, n/prime/) cont, for which the contribution to the fission rate in 238U and, therefore, in neutron multiplication per source neutron, may be considerable. The indeterminacy of the functionals, owing to the 15-20% inaccuracy of the spectra, is estimated for the hybrid reactor model studied to be 3-4.5% for the fission rate and 2-2.5% for the tritium yield
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Cover-to-cover translation of Atomnaya Ehnergiya (USSR).
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Journal Article
Journal
Soviet Atomic Energy; ISSN 0038-531X;
; v. 49(2); p. 509-515

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Wootan, D.W.; Rawlins, J.A.; Dobbin, K.D.
Hanford Engineering Development Lab., Richland, WA (USA)1984
Hanford Engineering Development Lab., Richland, WA (USA)1984
AbstractAbstract
[en] Results from the HP irradiation test have been shown to reduce uncertainties associated with calculation of axial and radial flux and reaction rate distributions, flux perturbations due to core heterogeneities, neutron flux and reaction rates outside the fuel region, activation of structural components and sodium, and fuel burnup. Improved knowledge of reaction rates (hence burnup, power and flux distributions) is expected to result in better prediction of the performance of experiments irradiated in FFTF
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May 1984; 23 p; Annual meeting of the American Nuclear Society; New Orleans, LA (USA); 3-8 Jun 1984; CONF-840614--53; Available from NTIS, PC A02/MF A01; 1 as DE84012378
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AbstractAbstract
No abstract available
Original Title
Vyvoj programu pro vypocet spekter neutronu z udaju integralnich detektoru
Source
Ceskoslovenska Akademie Ved, Prague. Ustav Dozimetrie Zareni; 159 p; Aug 1983; p. 125; 6. national symposium on radiation dosimetry; Marianske Lazne (Czechoslovakia); 28 Nov - 2 Dec 1983; Published in summary form only.
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AbstractAbstract
No abstract available
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Journal Article
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Nuclear Technology; v. 25(2); p. 330-348
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AbstractAbstract
[en] Two levels of neutron spectrometry are in regular use at nuclear power plants: some techniques used in the laboratory produce detailed spectra but require specialist operators, while simple instruments used by non-specialists to measure the neutron dose-rate to operators provide little spectral information. The standard portable instruments are therefore of no use when anomalous readings are obtained which require further investigation. AEA Technology at Winfrith has developed a Transportable Neutron Spectrometer (TNS) which is designed to produce reasonable spectra in routine use by staff with no specialist skill in spectroscopy, and high-quality spectra in the hands of skilled staff. The TNS provides a level of information intermediate between those currently available, and is also designed to solve the problem of imperfect dose response which is common in portable dosimeters. The TNS system consists of a power supply, a probe and a signal processing and data acquisition unit. (author)
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AbstractAbstract
[en] It has long been recognized that different neutron spectrum unfolding codes will produce significantly different results when unfolding the same measured data. In reviewing the results of such analyses it has been difficult to determine which result if any is the best representation of what was measured by the spectrometer detector. A proposal to develop a benchmarking procedure for spectrum unfolding codes is presented. The objective of the procedure will be to begin to develop a methodology and a set of data with a well established and documented result that could be used to benchmark and standardize the various unfolding methods and codes. It is further recognized that development of such a benchmark must involve a consensus of the technical community interested in neutron spectrum unfolding
Source
Trubey, D.K. (comp.); Oak Ridge National Lab., Tenn. (USA); p. 235-245; Oct 1976; Seminar on radiation energy spectra unfolding; Oak Ridge, Tennessee, United States of America (USA); 12 Apr 1976
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