Author: P. G. AndersonPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Proposal for the first irradiation of the new 43-element canflex geometry fuel bundles in the s-228 string as u2c-361 with the continued irradiation of materials test bundles afv and afy in the s-225 string as u2d-518 in the u-2 loop outlet test section
Author: P. G. AndersonFabrication data for canflex uo2 fuel pellets (natural and 2.59 w/o u-235 enrichment).
Author: M. R. HoareFabrication data for canflex UO2 fuel pellets (natural and 2.59 w/o 235U enrichment) : technical memorandum
Author: M. R. HoareCanflex fuel development project. canflex mk 1 fuel fabrication manufacturing operating procedures element profilometry
Author: B. A. SurettePublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Stress corrosion cracking can potentially cause fuel failures at circumferential ridges in the sheath. finite element computer codes elestres and feast are used to calculate two-dimensional, axisymmetric, elastic-plastic sheath stresses at and near the circumferential ridges. the level of stresses is given by the fuel design (such as pellet/sheath diameters, pellet length, pellet density) and by the operating conditions (such as power history). the accuracy, convergence, and cost of the stress calculations, however, are determined by the discretization used in the calculations: the number of nodes in the finite element mesh; the shape of the individual finite elements; the pattern into which the finite elements are arranged; and the size of the calculation-steps into which the power history is subdivided. in this study, we determined the discretization that gives a reasonable compromise of accuracy, convergence, and cost for the stress calculations. the highest accuracy is obtained by using triangular finite elements of aspect ratios close to one, and assembling them into hexagonal patterns. to caputure the stress gradients, five nodes are required across the sheath wall at the ridge, but two nodes are sufficient near the midplane of the pellet. the resulting mesh contains about 200 nodes and about 300 finite elements. calculation-steps of 6 kw/m provide a convergent solution, with a factor of two margin against numerical divergence. with the above arrangement, feast needs about 2.4 seconds on a cdc/cyber 175 computer to calculate sheath stresses per calculation-step. six radial nodes at the ridge would double the computing cost. decreasing the size of the calculation-steps means more calculations are needed to analyze a given power history, giving a linear increase in computing cost.
Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors
Author: International Atomic Energy AgencyPublisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 100
Book Description
The reactors around the world have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts worldwide. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.
Minor Actinide Burning in Thermal Reactors
Author: Alternative Automotive Fuels
Author: United States. Congress. House. Committee on Energy and Commerce. Subcommittee on Energy and PowerPublisher:
ISBN:
Category : Alcohol as fuel
Languages : en
Pages : 820
Book Description
Power Reactor Technology
Author: The First Nuclear Era
Author: Alvin M. WeinbergPublisher: Springer Science & Business Media
ISBN: 1563963582
Category : Biography & Autobiography
Languages : en
Pages : 326
Book Description
The autobiography of a highly influential nuclear engineer and scientist whose work began in the 1940s and continues today. He recounts his education, his role in the Manhattan Project, his stint as director of the Oak Ridge National Laboratory (1955- 73), and his subsequent work with both successful and unsuccessful commercial power reactors. Annotation copyright by Book News, Inc., Portland, OR
Nuclear Engineering Handbook
Author: Kenneth D. KokPublisher: CRC Press
ISBN: 1315356309
Category : Science
Languages : en
Pages : 1328
Book Description
Building upon the success of the first edition, the Nuclear Engineering Handbook, Second Edition, provides a comprehensive, up-to-date overview of nuclear power engineering. Consisting of chapters written by leading experts, this volume spans a wide range of topics in the areas of nuclear power reactor design and operation, nuclear fuel cycles, and radiation detection. Plant safety issues are addressed, and the economics of nuclear power generation in the 21st century are presented. The Second Edition also includes full coverage of Generation IV reactor designs, and new information on MRS technologies, small modular reactors, and fast reactors.