ON A SIMPLE SOLUTION OF THE GENERAL MULTIGROUP NEUTRON DIFFUSION EQUATIONS
Journal Article
·
· Istanbul Teknik Universitesi Bulteni (Turkey)
OSTI ID:4146684
The solution of the most general integro-differential equations for multigroup neutron diffusion is given for onegroup neutrons in finite multiplicative media taking delayed neutrons into consideration. The criticality condition is obtained, and an explicit expression is derived for a flux distribution initiated by sending given neutron fluxes to certain points of the medium. (auth)
- Research Organization:
- TEchnical Univ., Istanbul
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- NONE;
- NSA Number:
- NSA-18-002785
- OSTI ID:
- 4146684
- Journal Information:
- Istanbul Teknik Universitesi Bulteni (Turkey), Journal Name: Istanbul Teknik Universitesi Bulteni (Turkey) Vol. Vol: 16; ISSN ITEKA
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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