Fuel burn-up predictions in thermal reactors
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Fuel burn-up predictions in thermal reactors proceedings of a panel held in Vienna, 10-14 April,1967. by International Atomic Energy Agency.

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Published by I. A. E. A. in Vienna .
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Open LibraryOL20176340M

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Simple Model of Fuel Depletion. Fuel Reprocessing and Recycling Composition of Recycled LWR Fuel. Physics Differences of MOX Cores. Physics Considerations with Uranium Recycle. Physics Considerations with Plutonium Recycle. Reactor Fueling Characteristics. Radioactive Waste Radioactivity. Hazard Potential. Risk Factor.   Summary 12 The latest design calculation methods for thermal systems, both gas and water cooled, are based on the use of the code WIMS which uses nuclear data derived from basic tabulations* The present comparison of measured and predicted heavy isotope compositions for clusters irradiated in the SGBWB provides not only a test of the validity. For example, for a typical nuclear reactor with a thermal power of 3, MWth, about ~1, MWe of electrical power is generated in the generator. For example, a reactor with , kg of fuel operating at MWth power level for 1, days would have a burnup increase of 30, MWd/MTU. It will operate flexibly to follow loads, have fuel burn-up of 65 GWd/t and a high thermal efficiency, of 37 percent, and net efficiency of 36 percent. It is capable of using a full core load of MOX. Availability is, expected to be 92 percent over a year service life.

You can write a book review and share your experiences. Other readers will always be interested in your opinion of the books you've read. Whether you've loved the book or not, if you give your honest and detailed thoughts then people will find new books that are right for them. Fuel Depletion – Isotopic Changes Isotopic changes of 4% uranium fuel as a function of fuel burnup. As a reactor is operated at significant power, atoms of fuel are constantly consumed, resulting in the slow depletion of the must be noted there are also research reactors, which have very low power and the fuel in these reactors does not change its isotopic composition. al. ( and () developed the analytical approximation and numerical solution of the point nuclear reactor kinetics equations with average one-group of delayed ۳ neutron and the adiabatic.   If a nuclear reactor is assumed to have a recoverable energy per fission of MeV, calculate the fuel burnup and consumption rates in g/MWd for: (a) thermal reactors fueled with U or Pu; and (b) fast reactors fueled with Pu. [Note: In part (b), take the capture-to-fission ratio to be ] 2. The attempt at a solution.

A more general classification for reactors adopting thermal, moderated neutrons is. transuranic elements accumulated during the fuel burn up period, as well as Book. Full-text available. Experimental Nuclear Reactor Analysis: Theory, Numerical Models and Experimental Analysis presents a consolidated resource on reactor analysis, comprising theoretical concepts of reactor physics, dynamics and thermal-hydraulics. Each element is applied to predict the behaviour of the TRIGA test reactor and its validation with the experimental data. The highest average fuel burn-up attainable within the % enrichment limit is approximately 65 GWd/t and this would have to be extended to about % to reach a burn-up of GWd/t in pressurised water reactors (PWRs). However, to reach this burn-up, the maximum fuel rod enrichment in BWR assemblies will need to. There are no rigid requirements about the ratio of fast reactors to thermal reactors in a nuclear energy system with a closed fuel cycle. 2. There are no rigid requirements on the speed of spent fuel reprocessing. 3. One possible mode uses direct burial of spent fuel with high burnup (> 90%). 4.