Proposed graphite coring patterns for B, D, F, DR, and H Reactors

Technical Report · Thu Jun 20 04:00:00 EDT 1963

DOI:https://doi.org/10.2172/10151788· OSTI ID:10151788

Agar, J D

Heat transfer calculations were performed with the aid of the IBM 7090 to determine whether or not feasible graphite channel coring patterns could be adopted at the five older Hanford Reactors. The purpose of front and rear process channel coring is to significantly reduce or eliminate net expansion of the fringe graphite by raising the operating temperature above the annealing temperature of 300{degree}C. The results of the study show that such coring patterns are possible. Also, it was found to be possible, and indeed desirable, to standardize the patterns into one front face coring pattern and one rear face coring pattern for all five of the reactors: B, D, F, DR, and H. The resulting coring patterns are presented. These coring patterns will significantly reduce the net rate of expansion in the filler blocks and consequently reduce the inlet and outlet humps in the process channels. This will allow standard 8-inch fuel elements to be charged in all tubes. The afore-mentioned coring patterns will limit the pile gas atmosphere to a range of between 90% He - 10% CO{sub 2} and 100% He. If a greater percentage of CO{sub 2} were used following the adoption of the coring patterns, the possibility of exceeding the maximum graphite temperature limit in the fringes would exist with reactor operation at the same or higher power level. It is recommended that the rear coring be done simultaneously with the front coring. Future reactor power level increases will not be restricted as a direct result of the proposed coring patterns. The primary effect will be to reduce the front-to-rear graphite temperature gradients. The present limitations to power level increases would still be the limiting conditions after the completion of the channel coring.

• Research Organization: General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 10151788
• Report Number(s): HW--77985; ON: DE94011985
• Country of Publication: United States
• Language: English

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EXPERIMENTAL DATA
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RESEARCH
TEST
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MATERIALS TESTING REACTORS