RADIATION DOSIMETRY OF A GRAPHITE MODERATED RADIUM BERYLLIUM SOURCE.
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measurements have also been made in the air outside of the pile, while the Radium-Beryllium neutron source was being withdrawn from the pile.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. (BNL), Upton, NY (United States)
- Sponsoring Organization:
- USDOE Office of Energy Research (ER) (US)
- DOE Contract Number:
- AC02-98CH10886
- OSTI ID:
- 801698
- Report Number(s):
- BNL-69337; R&D Project: EST003NEFA; KB0301042; TRN: US0203988
- Resource Relation:
- Conference: 11TH INTERNATIONAL SYMPOSIUM ON REACTOR DOSIMETRY, BRUSSELS (BE), 08/18/2002--08/23/2002; Other Information: PBD: 18 Aug 2002
- Country of Publication:
- United States
- Language:
- English
Similar Records
Dosimetric characterization of two radium sources for retrospective dosimetry studies
Absolute Dosimetry Model of the University of Washington Clinical Neutron Therapy System (CNTS)