REACTOR SHIELD PENETRATIONS
Technical Report
·
OSTI ID:4293039
Differential energy spectra in various media for point isotropic sources of monoenergetic gamma radiation were obtained by a moments method solution of the Boltzmann transport equation. These data are utilized in a method developed for calculating gamma spectra and dose rates from nuclear reactors. An elemental volume of the reactor core is considered as a point isotropic source of gamma radiation with a spectrum which is defined at several energy levels. After penetration of each shield layer the modified spectrum is calculated and used as a source term for penetration of the next layer. For each iteration the calculation involves an integration over the source spectrum for each of the defined energy levels. After penetration of the final shield layer an integration is performed over the volume of the reactor core. Dose rate is obtained by applying the appropriate response function and performing an integration over the energy range. Results ob tained with this method agree with BSF centerline dose rates, for example, within 10% out to 120 cm in water and within 30% out to 380 cm in water. (auth)
- Research Organization:
- Convair, Fort Worth, Tex.
- NSA Number:
- NSA-13-009098
- OSTI ID:
- 4293039
- Report Number(s):
- FZM-913A
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
Similar Records
Fast-neutron Spectra and Dose-rate Calculations
FAST-NEUTRON AND GAMMA SPECTRA FOR BSR
CALCULATING GAMMA SPECTRA FROM REACTORS
Journal Article
·
Sat Dec 31 23:00:00 EST 1960
· Health Physics
·
OSTI ID:4025545
FAST-NEUTRON AND GAMMA SPECTRA FOR BSR
Journal Article
·
Mon Feb 29 23:00:00 EST 1960
· Nucleonics (U.S.) Ceased publication
·
OSTI ID:4207515
CALCULATING GAMMA SPECTRA FROM REACTORS
Journal Article
·
Mon Feb 29 23:00:00 EST 1960
· Nucleonics (U.S.) Ceased publication
·
OSTI ID:4184568