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Development of an alanine dosimeter for gamma dosimetry in mixed environments -- Summary of research

Technical Report ·
DOI:https://doi.org/10.2172/10146720· OSTI ID:10146720
 [1];  [2]
  1. Sandia National Labs., Albuquerque, NM (United States). Nuclear Facilities and Diagnostics Dept.
  2. Sandia National Labs., Albuquerque, NM (United States). Nuclear Systems Research Dept.

L-{alpha}-alanine, a nontoxic polycrystalline amino acid, has been investigated for use in high-precision, high-level absorbed-dose measurements in mixed neutron/photon environments such as research and test reactors. The technique is based on the use of electron paramagnetic resonance spectroscopy to determine the extent of free radical production in a sample exposed to ionizing radiation, and has been successfully used for photon absorbed-dose measurements at levels exceeding 10{sup 5} Gy with high measurement precision. Application of the technique to mixed environments requires knowledge of the energy-dependent response of the dosimeter for both photons and neutrons. Determination of the dosimeter response to photons is accomplished by irradiations in {sup 60}Co and bremsstrahlung sources and by calculations of energy-dependent photon kerma. Neutron response is determined by irradiations in conjunction with CaF{sub 2}:Mn thermoluminescence dosimeters and by calculations of energy-dependent neutron kerma. Several neutron environments are used, including those provided by the Annular Core Research Reactor and Sandia Pulsed Reactor.

Research Organization:
Sandia National Labs., Albuquerque, NM (United States)
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
AC04-94AL85000
OSTI ID:
10146720
Report Number(s):
SAND--94-0202; ON: DE94011002; BR: GB0103012
Country of Publication:
United States
Language:
English

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