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Gubbins, M.E.; Sherwin, J.
UKAEA Reactor Group, Winfrith. Atomic Energy Establishment1973
UKAEA Reactor Group, Winfrith. Atomic Energy Establishment1973
AbstractAbstract
No abstract available
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Nov 1973; 31 p
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Clarke, R.H.
Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs1970
Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs1970
AbstractAbstract
No abstract available
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Jun 1970; 22p
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AbstractAbstract
[en] A definition of the effective number density of lumped isotope chains is proposed and its physical interpretation discussed. As the first integral of the system of depletion equations, it is claimed to be the most consistent argument in terms of which the pseudo-isotopes effective group cross-sections should be tabulated. (author)
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AbstractAbstract
[en] Efforts exist to increase the burnup of fuel to be replaced (recharged) in the reactor. Extension of the recharging cycle makes the operation more economical. However, this calls for increasing the235U enrichment above 5%. This brings about problems in the various parts of the fuel cycle, which must be analyzed. The article outlines major barriers to reactor operation with fuel with enrichment over 5%, which must be addressed before this operating mode is approved. (author)
Original Title
Aspekty použití paliva s obohacením nad 5%
Primary Subject
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PROJECT TE01020455; 3 figs., 11 refs.
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Journal Article
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Energetika (Prague); ISSN 0375-8842;
; v. 65(1); p. 31-34

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ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, BURNUP, ENERGY SOURCES, EVEN-ODD NUCLEI, FUELS, HEAVY NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MATERIALS, MINUTES LIVING RADIOISOTOPES, NEUTRON ABSORBERS, NUCLEAR POISONS, NUCLEI, RADIOISOTOPES, REACTOR MATERIALS, SPONTANEOUS FISSION RADIOISOTOPES, URANIUM ISOTOPES, YEARS LIVING RADIOISOTOPES
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Incentives for the allowance of ''burnup credit'' in the design of spent nuclear fuel shipping casks
Sanders, T.L.; Westfall, R.M.; Jones, R.H.
Sandia National Labs., Albuquerque, NM (USA); Oak Ridge National Lab., TN (USA); Jones (R.H.), Los Gatos, CA (USA)1987
Sandia National Labs., Albuquerque, NM (USA); Oak Ridge National Lab., TN (USA); Jones (R.H.), Los Gatos, CA (USA)1987
AbstractAbstract
[en] An analysis has been completed which indicates that the consideration of spent fuel histories ('burnup credit') in the criticality design of spent fuel shipping casks could result in significant public risk benefits and cost savings in the transport of spent nuclear fuel. Capacities of casks could be increased considerably in some cases. These capacity increases result in lower public and occupational exposures to ionizing radiation due to the reduced number of shipments necessary to transport a given amount of fuel. Additional safety benefits result from reduced non-radiological risks to both public and occupational sectors. In addition, economic benefits result from lower in-transit shipping costs, reduced transportation fleet capital costs, and fewer cask handling requirements at both shipping and receiving facilities
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1987; 21 p; Waste management '87; Tucson, AZ (USA); 1-5 Mar 1987; TTC--0717; CONF-870306--14; Available from NTIS, PC A02/MF A01 as DE87005851
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Stockman, Christine T.; Alsaed, Halim A.; Bryan, Charles R.; Marschman, Steven C.; Scaglione, John M.
Idaho National Laboratory (INL), Idaho Falls, ID (United States). Funding organisation: USDOE Office of Nuclear Energy - NE (United States)2015
Idaho National Laboratory (INL), Idaho Falls, ID (United States). Funding organisation: USDOE Office of Nuclear Energy - NE (United States)2015
AbstractAbstract
[en] This report provides a technically based gas sampling frequency strategy for the High Burnup (HBU) Confirmatory Data Project. The evaluation of: 1) the types and magnitudes of gases that could be present in the project cask and, 2) the degradation mechanisms that could change gas compositions culminates in an adaptive gas sampling frequency strategy. This adaptive strategy is compared against the sampling frequency that has been developed based on operational considerations.
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1 May 2015; 43 p; OSTIID--1364086; AC07-05ID14517; Available from https://inldigitallibrary.inl.gov/sites/sti/sti/7245488.pdf; PURL: http://www.osti.gov/servlets/purl/1364086/
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AbstractAbstract
[en] The MOX fuel rods irradiated in the frame of Belgonucleaire's R and D program behaved satisfactorily and at least as well as UO2 rods, up to burn-ups beyond 60000 MWd/t. From the results so far, one may conclude that additional data should be obtained to better predict and understand the fission gas release behavior of the present industrial MOX fuel pellets obtained by the MIMAS (Micronization of a Master blend) process. In particular, more data are needed on: high burn-up behavior of MIMAS fuel (above 40000 MWd/t); understanding of the influence of the fuel microstructure (including the type and characteristics of UO2 powder) on the in-pile (mainly thermal) behavior; MOX fuel chemistry behavior at high burn-up, in relation to cycling, fission gas release and internal cladding corrosion; helium production and release in MOX rods and contribution to the internal pressure. The good understanding of the MOX behavior will not only allow improvements in the models used for its prediction and licensing but also in the fabrication process and the design characteristics. Core data will also be complemented by new basic experiments on representative MOX fuel from a neutronic point of view, needed to improve models and computational aids. 3 figs., 1 tab
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AbstractAbstract
No abstract available
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Israel Atomic Energy Commission, Tel Aviv; p. 41; Jul 1981; p. 41; Published in summary form only.
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AbstractAbstract
[en] The numerous steps of the fuel cycle each have their own technicalities and for each of them safety evaluations have been conducted. However, the fuel cycle should be seen as a whole, i.e. as one single ''system'', not only as a sequence of steps
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International Atomic Energy Agency, Vienna (Austria); Argonne National Lab., IL (USA); 673 p; Apr 1990; p. 469-470; International workshop on the safety of nuclear installations of the next generation and beyond; Chicago, IL (USA); 28-31 Aug 1989
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Sowerby, M.G.
1. Technical meeting on the nuclear transmutation of actinides. Ispra, Italy, 16-18 April 19771978
1. Technical meeting on the nuclear transmutation of actinides. Ispra, Italy, 16-18 April 19771978
AbstractAbstract
[en] Recent work at AERE, Harwell on the selection of nuclear incineration strategies will be reviewed. In particular the factors which influence the strategies will be discussed and a comparison will be made of the problems associated with a number of the strategies. From this discussion the more promising strategies which should be investigated in more detail will be identified
Primary Subject
Source
Commission of the European Communities, Ispra (Italy). Joint Research Centre; p. 237-245; 1978; p. 237-245; 1. Technical meeting on the nuclear transmutation of actinides; Ispra, Italy; 16 - 18 Apr 1977
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