By M. D. Brough, C. T. Chudley (auth.), Jeffery Lewins, Martin Becker (eds.)
The Editors enjoy providing an additional vol ume of their Annual evaluation sequence. the current quantity con tains six papers that could be stated to span from the speculation of layout to the perform of operation of recent nuclear strength stations, for this reason targeting nuclear power as a resource of electric strength. beginning with the main mathem atical, and continuing towards expertise, we've the Chudley and Brough account of a brand new interpretation of (linear) Boltzmann delivery thought by way of the attribute or ray procedure. This appears new in software right here, yet after all the tactic is the kid of many classical reports within the answer of partial differen tial equations and proves to remarkably well-suited to trendy desktops and their numerical bases. we'd placed the thing by means of Dickson and Doncals at the layout of heterogeneous cores subsequent, with its importance for quick reactors of the longer term. a number of the "central worthy" discrepancies, with their implication for safeguard and relia bility based on, inter alia, the Doppler impact, have made this a big sector for solution: to work out that we will be able to improve layout tools and codes that might reconcile concept and exper,. . . iment to the purpose at which theoretical designs will be approved for development with out the necessity for a full-scale mock up, as needed to be performed within the 1950's for the sunshine water re actors.
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DONCALS terns without exceeding peak linear power limitations in the fuel and blanket assemblies, while achieving a specified breeding ratio. The homogeneous core has 198 fuel assemblies that are subdivided into two enrichment zones to minimize the radial power-peaking factor. The fuel zone is surrounded by approximately 2 1/2 rows of radial blankets and four rows of removable shield assemblies employing Inconel rods in a stainless steel duct. The fuel assembly structural member is a hexagonal stainless steel duct containing 217 fuel rods in a triangular array.
The ability to design with a single fuel enrichment (~25%) neutron fluences The single most detrimental characteristic was that the fuel inventory was increased by approximately 25%. However, the resulting enrichment was approximately the same as utilized in the outer core zone of the homogeneous concept during the equilibrium cycle. In addition, subsequent analysis(27) performed at the Argonne National Laboratory showed that this heterogeneous CRBRP had an improved response to hypothetical accident transients not terminated by the plant protection system.
Considerable effort is still underway. One reason the French favor the heterogeneous concept is that it provides a means of using Phenix-tested fuel pins 44 P. W. DICKSON AND R. A. DONCALS in their larger commercial designs. A heterogeneous design provides many of the same effects as would the use of a larger fuel pin diameter withou~ the development costs associated with developing fuel with a larger pin diameter. In the United states, testing of larger pin diameters already has been initiated for commercial reactors.