Gamma-ray dose at shield-tissue interfaces and buildup factor implications
Buildup factors continue to be widely used for gamma-ray shield design, but there are several problems in application. Shure has pointed out the need for buildup factors to be consistent with the ANSI standard flux-to-dose factors. However, consistent buildup factor data cannot be obtained by simply integrating the ANSI response function over infinite-medium spectra, because this function gives the response at various depths in a tissue phantom for a gamma ray of a certain energy entering the phantom. The ANSI response function can only be applied to a spectrum emerging from a shield as determined from a transport calculation. In order to evaluate the dose in tissue from gamma rays which have penetrated a shield, a detailed transport study was undertaken at the Safety Research Laboratory at Kalpakkam in collaboration with the Radiation shielding Information Center. Computations were made using the one-dimensional transport code ASFIT which has recently been extended to treat the secondary sources of fluorescence and bremsstrahlung. Results are reported. (WHK)
- Research Organization:
- Oak Ridge National Lab., TN (USA); Reactor Research Centre, Kalpakkam (India). Safety Research Lab.
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5261486
- Report Number(s):
- CONF-820609-54; ON: DE82017499; TRN: 82-017258
- Resource Relation:
- Conference: American Nuclear Society annual meeting, Los Angeles, CA, USA, 6 Jun 1982
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
GAMMA RADIATION
BUILDUP
LEAD
TISSUE-EQUIVALENT MATERIALS
INTERFACES
RADIATION DOSES
SHIELDING
TISSUES
BODY
DOSES
ELECTROMAGNETIC RADIATION
ELEMENTS
IONIZING RADIATIONS
MATERIALS
METALS
RADIATIONS
655003* - Medical Physics- Dosimetry
654002 - Radiation & Shielding Physics- Shielding Calculations & Experiments- (-1987)