Results 231 to 240 of about 20,584 (276)
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Inelastic cross-sections for fission-spectrum neutrons-I

Journal of Nuclear Energy (1954), 1956
Abstract The general problem of determining inelastic cross-sections from sphere transmission measurements is considered. Experimental problems encountered in this type of investigation are discussed. Analytical methods of correcting for multiple scattering and other important effects in spherical shells are presented.
Bethe, H. A.   +2 more
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The tail of the fission spectrum for 235U and 252Cf

Annals of Nuclear Energy, 1986
Dosimetry reaction-rate measurements made in the 252Cf and 235U fields are used in the stay'sl code to unfold the fission spectra. It is conceivable that the tail of the fission spectrum can not be represented by a smooth function.
R.P. Corcuera, A.D. Caldeira
openaire   +1 more source

Spectrum and yield of prompt232Th fission neutrons

Soviet Atomic Energy, 1991
investigations of these spectra has increased on the other. However, the scattering of data and the errors in these data are large, which is connected with the difficulties such measurements involve. Therefore, further measurements of spectra of fission neutrons at different energies are necessary, both for determining the adequacy of theory for ...
A. V. Polyakov   +5 more
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Neutrons for fission-track dating and fission tracks for neutron spectrum monitoring

Acta Physica Hungarica, 1994
An account is given of our experiences in the absolute calibration of Fission Track dating, based on coirradiation with the sample either of metal monitors or of uranium-doped glass monitors. Secondly, the (Corning) CN3 and CN5 glasses, with a largely different Th/U ratio, were used to characterize the neutron spectrum in channel 4 of reactor Thetis ...
F. Bellemans   +2 more
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A Sodium-Cooled Thermal-Spectrum Fission Battery

Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, 2021
Abstract We propose a low-enriched-uranium, thermal-neutron-spectrum sodium-cooled reactor with a peak sodium temperature of 700°C coupled to an air-Brayton power cycle for electricity and heat. Three low-enriched-uranium, thermal spectrum sodium-cooled reactors were built in the 1960s and 1970s; but there has been no examination of such
Patrick J. McDaniel, Charles Forsberg
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Spectrum of carbonaceous-chondrite fission xenon

Geochimica et Cosmochimica Acta, 1976
Estimations of the fission spectrum in xenon isotopes from the progenitor of the strange carbonaceous-chondrite xenon must take account of p-process nucleosynthesis if the latter is the source of anomalous Xe-124, 126. Sample calculations of the p-process yields illustrate the magnitude of the effect, which can greatly increase the estimated Xe-132 ...
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Evaluation of Uncertainties of 235U Fission Spectrum

1985
This paper presents a first attempt of uncertainty evaluation for the 235U fission spectrum. The covariance matrix, in 15 energy groups, has been obtained from fission rate measurements performed in Mbl cavity in collaboration between NBS and SCK/CEN.
M. Petilli, D. M. Gilliam
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Representation of the Fission Spectrum and Multiplication Calculations

1992
We investigated the different representations of the fission process as total fission on one hand and as the sum of direct fission, first chance fission, second, third and fourth chance fission on the other hand (MT = 18 versus MT = 19, 20, 21 and 38 in ENDF terminology).
R. L. Perel, J. J. Wagschal
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The Neutron Spectrum from a Fission Source in Graphite

Nuclear Science and Engineering, 1969
Time-of-flight measurements of the neutron angular flux spectrum in graphite have been made to provide a standard of comparison for neutron penetration calculations.
A. E. Profio   +2 more
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Spin-Dependent Calculation of Fission Neutron Spectra and Fission Spectrum Integrals for Six Fissioning Systems

Nuclear Science and Engineering, 1989
Calculations of fission neutron spectra and fission spectrum integrals for six fissioning systems are reported. The systems studied are thermal-neutron-induced fission of /sup 233/U, /sup 235/U, and /sup 239/Pu; 2-MeV neutron fission of /sup 232/Th and /sup 238/U, and spontaneous fission of /sup 252/Cf.
openaire   +1 more source

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