Neutron interaction data in carbon derived from measured and calculated ionisation yield spectra
- 1. Universitaet des Saarlandes, Homberg/Saar (Germany, F.R.). Fachrichtung Biophysik und Physikalische Grundlagen der Medizin
- 2. Physikalisch-Technische Bundesanstalt, Braunschweig (Germany, F.R.)
Description
The analysis of measured and calculated ionisation yield spectra for neutrons can be used for the investigation of dosimetric quantities and of basic interaction data for single elements. First results obtained with A-150 plastic (78% carbon by weight) and with graphite counters showed that measured carbon kerma factors for high energy neutrons are significantly lower than the calculated values. Measured and calculated ionisation yield spectra for carbon were analysed at 15 and 17 MeV neutron energy with special attention given to the (n,n'3α) reaction. The partial kerma factor for this process was evaluated from the experiments taking account of experimental artefacts (wall effects) and of the ionisation produced by charged particles originating in elastic scattering, inelastic scattering and in (n,α) reactions. The results show that the calculated partial kerma factors would have to be reduced by 30% at 15 MeV and by 50% at 17 MeV neutron energy in order to match the evaluated experimental partial kerma factors. (author)
Additional details
Publishing Information
- Journal Title
- Radiat. Prot. Dosim.
- Journal Volume
- 13
- Journal Issue
- 1-4
- Series
- Radiat. Prot. Dosim.
- Journal Page Range
- 13-17
- ISSN
- 0144-8420
- CODEN
- RPDOD
Conference
- Title
- 9. symposium on microdosimetry.
- Dates
- 20-24 May 1985.
- Place
- Toulouse (France).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 17038314
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CARBON; COMPARATIVE EVALUATIONS; CROSS SECTIONS; IONIZATION; KERMA; MEV RANGE 10-100; MICRODOSIMETRY; NEUTRON DOSIMETRY; NEUTRON REACTIONS; NEUTRON SPECTRA; PROPORTIONAL COUNTERS
- Descriptors DEC
- BARYON REACTIONS; DOSIMETRY; ELEMENTS; ENERGY RANGE; EVALUATION; HADRON REACTIONS; MEASURING INSTRUMENTS; MEV RANGE; NONMETALS; NUCLEAR REACTIONS; NUCLEON REACTIONS; RADIATION DETECTORS; SPECTRA