Actions for Mobile prompt-gamma in vivo neutron activation facility. [
Mobile prompt-gamma in vivo neutron activation facility. [/sup 238/Pu, Be] [electronic resource].
- Published
- Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1978.
- Physical Description
- Pages: 17 : digital, PDF file
- Additional Creators
- United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- This report describes the development and fabrication of a self-contained ''neutron-capture'' facility in a mobile trailer which is readily transportable. Although the initial project was designed for the measurement of Cd deposited in the liver and kidney of industrial workers, the sensitivity of the system will allow for measurements in normal populations. The limits of detection of Cd are 2.0 mg for kidney and 1.5 ..mu..g/g (wet weight) for liver (associated organ radiation dose is 660 mrem). The portable facility makes it possible to study Cd exposed populations in any geographic location. With minor modifications of the collimator, detectors and counting geometry, it is also possible to make in-vivo measurements of total body nitrogen. The neutron source used in the mobile facility is 85 Ci /sup 238/Pu,Be shielded by epoxy resin doped with LiCO/sub 3/ and /sup 6/LiF. Additional shielding is provided by Pb bricks and polyethylene bricks with 1% boron and 80% Pb. For Cd measurements, the detection system consists of two Ge(Li) detectors (25% efficiency each) shielded by bismuth and a 1.5 cm layer of paraffin heavily doped with /sup 6/LiF. For body nitrogen, two shielded 15.2 x 15.2 cm NaI(Tl) detectors are positioned above the scanning bed. This mobile activation facility could be usefully employed in countries which need to monitor industrial populations but which do not have ready access to large neutron research facilities and permanently installed whole-body counters.
- Report Numbers
- E 1.99:bnl-24290
E 1.99: conf-780538-2
conf-780538-2
bnl-24290 - Subject(s)
- Other Subject(s)
- Cadmium
- Activation Analysis
- Irradiation Plants
- Design
- Neutron Sources
- Neutrons
- Portable Sources
- Beryllium
- Capture
- Collimators
- Gamma Radiation
- Human Populations
- Neutron Reactions
- Nitrogen
- Plutonium 238
- Radiation Detectors
- Shielding
- Transport
- Actinide Isotopes
- Actinide Nuclei
- Alkaline Earth Metals
- Alpha Decay Radioisotopes
- Baryon Reactions
- Baryons
- Chemical Analysis
- Cryogenic Fluids
- Electromagnetic Radiation
- Elementary Particles
- Elements
- Even-Even Nuclei
- Fermions
- Fluids
- Hadron Reactions
- Hadrons
- Heavy Nuclei
- Ionizing Radiations
- Isotopes
- Measuring Instruments
- Metals
- Nonmetals
- Nuclear Reactions
- Nuclei
- Nucleon Reactions
- Nucleons
- Particle Sources
- Plutonium Isotopes
- Populations
- Radiation Sources
- Radiations
- Radioisotopes
- Years Living Radioisotopes
- Note
- Published through SciTech Connect.
01/01/1978.
"bnl-24290"
" conf-780538-2"
Symposium on nuclear activation techniques in the life sciences, Vienna, Austria, 22 May 1978.
Cohn, S.H.; Ellis, K.J.; Vartsky, D.
Brookhaven National Lab., Upton, N.Y. (USA) - Funding Information
- EY-76-C-02-0016
View MARC record | catkey: 14403181