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U.S. Department of Energy
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CALCULATED THERMAL FLUX DISTRIBUTION IN AND AROUND SRE INPILE POISON RING TEST

Technical Report ·
OSTI ID:4843268
The neutron flax distribution around the Sodium Reactor Experiment inpile poison ring test was calculated, using the PDQ 2-dimensional neutron diffusion equation IBM704 code, for an axial and radial case. Figures are shown of the calculated axial flux distribution and the x-y profile of the region used for the horizontal flux distribution. (M.C.G.)
Research Organization:
Atomics International. Div. of North American Aviation, Inc., Canoga Park; Calif.
NSA Number:
NSA-15-028739
OSTI ID:
4843268
Report Number(s):
NAA-SR-Memo-3485
Country of Publication:
United States
Language:
English