A method of computing fission-product decay heat in a reactor with time-dependent flux PDF Download
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Author: F. W. Barclay
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: F. W. Barclay
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: JOHN V. NEHEMIAS, RALPH C.DENNIS, JOHN G. LEWIS, HAROLD A. CHLGREN
Publisher:
ISBN:
Category :
Languages : en
Pages : 35
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Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1396
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Author: Talmadge Ray England
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 696
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Author: Kern, Kilian
Publisher: KIT Scientific Publishing
ISBN: 3731508435
Category : Delayed neutrons
Languages : en
Pages : 254
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Author: Joseph M. Harrer
Publisher:
ISBN: 9780870790058
Category : Technology & Engineering
Languages : en
Pages : 1052
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Author:
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ISBN:
Category :
Languages : en
Pages :
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In the past five years there have been new experimental programs to measure decay heat (i.e., time dependent beta- plus gamma-ray energy release rates from the decay of fission products) following thermal-neutron fission of 235U, 239Pu, and 241Pu for times after fission between 1 and approx. 105 sec. Experimental results from the ORNL program stress the very short times following fission, particularly in the first few hundred sec. Complementing the experimental effort, computer codes have been developed for the computation of decay heat by summation of calculated individual energies released by each one of the fission products. By suitably combining the results of the summation calculations with the recent experimental results, a new Decay Heat Standard has been developed for application to safety analysis of operations of light water reactors. The new standard indicates somewhat smaller energy release rates than those being used at present, and the overall uncertainties assigned to the new standard are much smaller than those being used at present.
Author: Bruce Earl Koopmann
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 254
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"The development of a computer code was undertaken to calculate the fission product nuclide concentration for spent fuel discharged from a nuclear reactor, as a function of irradiation time, cooling time, neutron flux, and element cross section. The necessary input data was prepared from the basic nuclear data for fission of uranium-235 and plutonium-239. Calculations are also made for total or selective element beta heating and total gamma flux according to user selected input groups. These calculations would be useful in fuel element shielding, cooling, shipping and processing studies"--Abstract, leaf ii.
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 444
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Author:
Publisher:
ISBN:
Category : Computer programs
Languages : en
Pages : 650
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