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RADIATION DOSIMETRY OF A GRAPHITE MODERATED RADIUM BERYLLIUM SOURCE.

Conference ·
OSTI ID:801698
The Brookhaven National Laboratory Sigma Pile a Radium-Beryllium neutron source imbedded in a cube of graphite blocks. The pile is approximately 2.13 m on four sides and is 3.07 m high. Absolute and relative thermal neutron flux measurements have been made using gold and indium foils, which were both bare and cadmium covered. Thermo-luminescent dosimeters were used to determine the neutron and gamma-ray dose rates in the pile. Gamma-ray dose rate measurements have also been made in the air outside of the pile, while the Radium-Beryllium neutron source was being withdrawn from the pile. The Monte Carlo MCNP code has been used to calculate the coupled neutron-photon transport. Measured dose rates at various locations agreed with the calculated values within 5% to 15%.
Research Organization:
Brookhaven National Lab., Upton, NY (US)
Sponsoring Organization:
USDOE Office of Energy Research (ER) (US)
DOE Contract Number:
AC02-98CH10886
OSTI ID:
801698
Report Number(s):
BNL--69337; KB0301042
Country of Publication:
United States
Language:
English

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