SOME TRANSPORT THEORY AND MONTE CARLO CALCULATIONS ON THE NUCLEAR BEHAVIOR OF THE BORE

Technical Report · Tue Oct 25 04:00:00 EDT 1960

OSTI ID:4153092

Goodjohn, A J; Hinman, G W; Nickel, G H

The validity of simpler analytical tcchniques in calculating heavily loaded, heterogencous reactors of the type contemplated for the BORE was examined by a series of multigroup transport and Monte Carlo calculations. The complex space-energy flux variations in the typical reactor cell were investigated by the DSN one-dimensional, multigroup transport code in the thermal neutron energy range nial energy range (0.88-- 81.4 ev). A reactivity calculation for the complete reactor, core plus reflector, was performed using the DSN code and cross sections derived. from the cell calculations. Thc thermal cell calculation revealed significant variations from simpler one-group calculations. The disadvantage factor for the heterogeneous cell, for example, revealed the effects of neutron moderation by the diluent in the fuel element and of complicated source shape in a group calculation. Both of these effects add complications to any simple treatment. The Monte Carlo calculation of the epithermal range revealed complex energy-space flux variations that are not amenable to any simple analytical technique. (auth)

• Research Organization: General Atomic Div., General Dynamics Corp., San Diego, Calif.
• NSA Number: NSA-18-001237
• OSTI ID: 4153092
• Report Number(s): GAMD-1907
• Country of Publication: United States
• Language: English

Related Subjects

EBOR
GROUP THEORY
MONTE CARLO METHOD
NEUTRON FLUX
POWER PLANTS
REACTIVITY
REACTOR TECHNOLOGY
REACTORS
SLOWDOWN
THERMAL NEUTRONS
TRANSPORT THEORY
VARIATIONS