Analysis of the initial shielding design for the upflow gas-cooled fast reactor (GCFR)

Technical Report · Thu May 01 00:00:00 EDT 1980

DOI:https://doi.org/10.2172/5494352· OSTI ID:5494352

Slater, C. O.; Tomlinson, E. T.; Williams, L. R.

Presented are the results of a preliminary analysis of the initial shield design for a gas-cooled fast reactor in which the coolant flow has been reversed from downward to upward. Calculations were performed on two levels: (1) localized, heterogeneous cell calculations to determine the effects of radiation streaming, and (2) streaming-corrected full-model homogeneous calculations to obtain global radiation levels. The method used to obtain and apply the streaming factors is explained. The results indicate that with few exceptions the shielding design is very effective. Possible problems exist in (1) the core barrel, where the total neutron fluence limit of 10/sup 21/cm/sup -2/ is exceeded, and (2) the grid plate, where the neutron fluence is near the fluence limit predicted by damage function analysis.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5494352
• Report Number(s): ORNL/TM-7246; TRN: 80-008526
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
GCFR REACTOR
SHIELDING
GAS FLOW
NEUTRON FLUX
RADIATION STREAMING
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EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
GAS COOLED REACTORS
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HELIUM COOLED REACTORS
RADIATION FLUX
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