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Copeland, G.L.; Gambill, W.R.; Harrington, R.M.
Oak Ridge National Lab., TN (USA)1989
Oak Ridge National Lab., TN (USA)1989
AbstractAbstract
[en] The preconceptual design phase of the Advanced Neutron Source (ANS) Project ended with the selection of a reference reactor core that will be used to begin conceptual design work. The new reference core consists of two involute fuel elements, of different diameters, aligned axially with a small axial gap between them. The use of different element diameters permits a separate flow of coolant to be provided for each one, thus enhancing the heat removal capability and increasing the thermal-hydraulic margins. The improved cooling allows the elements to be relatively long and thin, so self-shielding is reduced and an acceptable core life can be achieved with a relatively small loading of highly enriched uranium silicide fuel clad in aluminium. The new reference design has a fueled volume 67.4 L, each element having a heated length of 474 mm and a radial fuel thickness of 66 mm. The end-of-cycle peak thermal flux in the large heavy-water reflector tank around the core is estimated to be in the range of 0.8 to 1.0 x 1020 m-2 · s-1. 7 refs., 23 figs., 15 tabs
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Aug 1989; 112 p; CONTRACT AC05-84OR21400; Available from NTIS, PC A06/MF A01 - OSTI as DE89016936; US Govt. Printing Office Dep
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