Calculation of neutron dose to polymeric materials and application of threshold-foil measurements

Journal Article · Thu Jan 01 04:00:00 EST 1981 · Annu. Book ASTM Stand.; (United States)

OSTI ID:5554158

The energy deposition, or dose, in polymeric materials from neutrons is the basic interest of this method and is accomplished by means of a calculation. The knowledge of the neutron spectrum and integrated fluxes, which can be obtained from the threshold-foil measurements, is sufficient for such a calculation. The method includes a discussion of the calculation of the neutron dose for a known neutron spectrum, for an unknown neutron spectrum, and from thermal neutron-capture reactions. A section on the measurement of integrated neutron fluxes with threshold foils includes experimental and calibration procedures, fission-foil and sulfur-foil calibration procedures, fission-foil and sulfur-foil calibration technique, and instrumentation and counting analysis procedures. (JMT)

• OSTI ID: 5554158
• Journal Information: Annu. Book ASTM Stand.; (United States), Journal Name: Annu. Book ASTM Stand.; (United States) Vol. 45; ISSN ABASC
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360406* -- Materials-- Polymers & Plastics-- Radiation Effects-- (-1987)
CALIBRATION
DOSES
DOSIMETRY
EQUIPMENT
FISSION FOIL DETECTORS
FLUX DENSITY
FOILS
INDUSTRY
MEASURING INSTRUMENTS
NEUTRON DETECTORS
NEUTRON DOSIMETRY
NEUTRON FLUX
NEUTRON SPECTRA
NUCLEAR INDUSTRY
POLYMERS
RADIATION DETECTORS
RADIATION DOSES
RADIATION FLUX
SPECTRA
STANDARDS