Published August 1989 | Version v1
Report Restricted

Advanced neutron source final preconceptual reference core design

Description

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

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A06/MF A01 - OSTI as DE89016936; US Govt. Printing Office Dep.

Files

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Additional details

Publishing Information

Imprint Pagination
112 p.
Report number
ORNL/TM--11234

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
21010733
Subject category
S07: ISOTOPES AND RADIATION SOURCES;
Descriptors DEI
HEAT TRANSFER; HYDRAULICS; NEUTRON FLUX; NEUTRON GENERATORS; NEUTRON SOURCES; REACTOR SAFETY; SPECIFICATIONS
Descriptors DEC
ENERGY TRANSFER; PARTICLE SOURCES; RADIATION FLUX; RADIATION SOURCES; SAFETY

Optional Information

Contract/Grant/Project number
Contract AC05-84OR21400