Fission-product Behavior in Ceramic Oxide Fuel PDF Download
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Author: Ian J. Hastings
Publisher:
ISBN:
Category : Ceramic materials
Languages : en
Pages : 320
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Book Description
Author: Ian J. Hastings
Publisher:
ISBN:
Category : Ceramic materials
Languages : en
Pages : 320
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Book Description
Author: W. L. Bunch
Publisher:
ISBN:
Category : Fast neutrons
Languages : en
Pages : 90
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Book Description
The fission product inventory and the decay heat associated with driver fuel irradiated to goal exposure (45,000 MWd per metric ton) in the Fast Test Reactor is presented, based on calculations using the computer code RIBD with a nuclear data library prepared for the FTR environment. Curie inventories as a function of decay time are given for each of about 350 isotopes or isomeric states generated by the fast-neutron induced fission of either 239Pu or 238U, by down-chain decay, or by subsequent neutron capture. Beta, gamma, and total decay power are given in percent of operating power for decay times from 1 sec to about 10 years. Uncertainty in the decay heat calculations, based on propagation of the uncertainties associated with input nuclear data, is estimated. The uncertainty is calculated to be less than +̲ 10% for the first 10 days, and less than +̲ 20% over a 10-yr decay period.
Author: R. C. Daniel
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 156
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Book Description
Author: P. J. Peterson
Publisher:
ISBN:
Category : Graphite as fuel
Languages : en
Pages : 50
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Book Description
Two type-AUC graphite fuel elements loaded by solution impregnation to an average concentration of 0.115 g/cc of 93.13% enriched U converted to UC and UC2 were irradiated at temperatures of about 1500 deg C to a 10.2% maximum burnup, corresponding to an irradiation level of 219 kwh/cc or 2.45 x 101 fissions/cc of fuel element. Post-irradiation measurements of the elements showed dimensional changes of -4.3 and -4.8% with the grain, and --0.8 to -2.5% across the grain. Weight losses were 3.2 and 5.1% for the individual elements with approximately 11% of the total U being lost from the elements. With-the- grain thermal conductivity at nominal room temperature was reduced by a factor of approximates 7 and electrical conductivities by factors of 3.4 to 8.3, also at room temperature. Impact strength appeared to be somewhat improved by irradiation. Migration of U within the element was detected by radiographic density observations but not evaluated quantitatively. As anticipated, fission product release was high.
Author: Eugene E. Gruber
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 36
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Book Description
Author:
Publisher: Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development
ISBN:
Category : Science
Languages : en
Pages : 572
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Book Description
Communicates the results of an international seminar which reviewed recent progress in the field of fission gas behaviour in light water reactor fuel and sought to improve the models used in computer codes predicting fission gas release. State-of-the-art knowledge is presented for both uranium-oxide and mixed-oxide fuels loaded in water reactors.
Author:
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 68
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Book Description
Author:
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 196
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Book Description
Author: J. T. Rogers
Publisher: CRC Press
ISBN: 1000158624
Category : Science
Languages : en
Pages : 742
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Book Description
The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this field in the most open and effective manner. Recognizing the roles of heat and mass transfer in all aspects of fission-product behavior in sever reactor accidents, the Executive Committee of the International Centre for Heat and Mass Transfer organized a Seminar on Fission Product Transport Processes in Reactor Accidents. This book contains the eleven of the lectures and all the papers presented at the seminar along with four invited papers that were not presented and a summary of the closing session.
Author: V. G. Trice
Publisher:
ISBN:
Category : Because of the small scale of the experiments and necessary exposure of the irradiated fuel to air in the cave facility, it was not possible to obtain definitive data on product yields
Languages : en
Pages : 50
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Book Description
The behavior of fission products was consistent with the earlier results. Fission product removals were over 99 per cent for krypton, xenon, iodine, cesium, barium, and strontium, over 95 percent for yttrium, rare earths, and tellurium, and zero for the noble metals.
