Thermal disadvantage factor; An efficient calculation
Journal Article
·
· Nuclear Science and Engineering; (USA)
OSTI ID:6655641
- Missouri Univ., Columbia, MO (USA). Dept. of Nuclear Engineering
A method is described where reactor cell flux and the disadvantage factor are calculated by using diffusion theory in the moderator and integral transport in the fuel. The method is efficient (noniterative) and provides results that agree well with Monte Carlo, P{sub 5} and ABH results.
- OSTI ID:
- 6655641
- Journal Information:
- Nuclear Science and Engineering; (USA), Journal Name: Nuclear Science and Engineering; (USA) Vol. 104:1; ISSN 0029-5639; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
Similar Records
THERMAL FLUX DISADVANTAGE FACTORS FOR SLAB GEOMETRY
Calculational method for thermal disadvantage factor (LWBR Development Program)
Nuclear reactor fuel cell burnup calculations; an efficient method
Journal Article
·
Wed Jan 31 23:00:00 EST 1962
· Nuclear Sci. and Eng.
·
OSTI ID:4800772
Calculational method for thermal disadvantage factor (LWBR Development Program)
Technical Report
·
Fri Sep 01 00:00:00 EDT 1967
·
OSTI ID:6761850
Nuclear reactor fuel cell burnup calculations; an efficient method
Thesis/Dissertation
·
Sat Dec 31 23:00:00 EST 1988
·
OSTI ID:6361689
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CALCULATION METHODS
EQUATIONS
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
RADIATION FLUX
REACTOR KINETICS EQUATIONS
TRANSPORT THEORY
220100* -- Nuclear Reactor Technology-- Theory & Calculation
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CALCULATION METHODS
EQUATIONS
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
RADIATION FLUX
REACTOR KINETICS EQUATIONS
TRANSPORT THEORY