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Reactor physics studies of various advanced neutron source reactor core configurations

Conference · · Transactions of the American Nuclear Society; (USA)
OSTI ID:6791336
 [1]
  1. Oak Ridge National Lab., TN (USA)
The current conceptual design for the core of the advanced neutron source (ANS) reactor is a vertically split, annular geometry composed of involute, thin (1.3-mm) fuel plates and thin (1.3-mm) heavy-water coolant channels. The core would have a heavy-water reflector, and estimates of the total fueled core volume have ranged from 30 to 60 {ell}. Due to control rod and materials irradiation position constraints, the inner radius of the annulus is expected to be at least 110 mm. A goal of the ANS project is to design a facility in which the peak thermal flux in the reflector is 5 to 10 {times} 10{sup 19} n/m{sup 2}{center dot}s. To achieve this goal while maintaining adequate thermal-hydraulic margins, a variety of core configurations have been proposed, two of which are shown. For both the two- and three-element designs, coolant flowing through any single element does not enter the other element(s). The use of three elements allows the length of each element to be smaller - reducing pressure drop and inlet/outlet temperature differential. However, the engineering complexity and cost of the three-element design exceeds that of the two-element design. This paper discusses the relative merits of these designs from a neutronics viewpoint.
OSTI ID:
6791336
Report Number(s):
CONF-890604--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 59
Country of Publication:
United States
Language:
English