Radiation dosimetry of a graphite moderated radium-beryllium source.
The Brookhaven National Laboratory Sigma Pile is 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. Thermoluminescent 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measurements have also been made in the air outside of the pile, while the radium-beryllium neutron source was being withdrawn from the pile.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 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%.
Holden
Norman E
NE
National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY 11973-5000, USA. holden@bnl.gov
Reciniello
Richard N
RN
Hu
Jih-Perng
JP
D000465:Algorithms; D001608:Beryllium / Q000032:analysis*; D001822:Body Burden; D005720:Gamma Rays; D006108:Graphite; D009502:Neutrons; D011829:Radiation Dosage; D011835:Radiation Protection / Q000379:methods*; D011868:Radioisotopes / Q000032:analysis; D011874:Radiometry / Q000295:instrumentation / Q000379:methods; D011883:Radium / Q000032:analysis*; D018570:Risk Assessment / Q000379:methods*; D013819:Thermoluminescent Dosimetry / Q000295:instrumentation* / Q000379:methods*
D011868:Radioisotopes; D006108:Graphite; D001608:Beryllium; D011883:Radium