Two-Group SRE Fluxes in Two Dimensions
- North American Aviation, Inc., Canoga Park, CA (United States). Atomics International Div.
Several two-group diffusion problems, representing the Sodium Reactor Experiment, were solved by means of NICK-2, a two-dimensional (r, z) multigroup diffusion code. The problems represented the following operational conditions: Wet criticality - 33 elements loaded and all components at a uniform temperature of 180 °C. Low temperature operation - 43 elements loaded, inlet coolant temperature 260 °C, and outlet coolant temperature 343 °C. High temperature operation - 43 elements loaded, inlet coolant temperature 260 °C, and outlet coolant temperature 516 °C. Two two-dimensional fluxes and power densities are given for the above cases. In addition, the results for reactivity and critical mass are compared with the results of the usual one-dimensional approximation, assuming separability of the fluxes in cylindrical coordinates. The close agreement obtained indicates that the one-dimensional approximation represents the two-dimensional situation quite well, even for high temperature operation.
- Research Organization:
- North American Aviation, Inc., Canoga Park, CA (United States). Atomics International Div.
- Sponsoring Organization:
- US Atomic Energy Commission (AEC); USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AT(11-1)-GEN-8
- NSA Number:
- NSA-13-015777
- OSTI ID:
- 4238048
- Report Number(s):
- NAA-SR--3515
- Country of Publication:
- United States
- Language:
- English
Similar Records
SRE CORE III FUEL ELEMENTS THERMAL ANALYSIS
MODERATOR HEAT TRANSFER ANALYSIS FOR SRE-PEP THIRD CORE
STARTING OPERATION OF THE SRE GRAPHITE REACTOR
Technical Report
·
Wed Feb 26 23:00:00 EST 1964
·
OSTI ID:4003996
MODERATOR HEAT TRANSFER ANALYSIS FOR SRE-PEP THIRD CORE
Technical Report
·
Sun Sep 01 00:00:00 EDT 1963
·
OSTI ID:4072518
STARTING OPERATION OF THE SRE GRAPHITE REACTOR
Journal Article
·
Mon Dec 31 23:00:00 EST 1956
· Atomnaya Energiya
·
OSTI ID:4329881
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTERS
CRITICALITY
DENSITY
DIFFUSION
ERRORS
FUEL ELEMENTS
GROUP THEORY
HIGH TEMPERATURE
LIQUID METAL COOLANT
LOW TEMPERATURE
MASS
Nuclear Criticality Safety Program (NCSP)
OPERATION
POWER
POWER PLANTS
PROGRAMMING
REACTIVITY
REACTOR FUELING
REACTORS
SODIUM
SRE
VARIATIONS
COMPUTERS
CRITICALITY
DENSITY
DIFFUSION
ERRORS
FUEL ELEMENTS
GROUP THEORY
HIGH TEMPERATURE
LIQUID METAL COOLANT
LOW TEMPERATURE
MASS
Nuclear Criticality Safety Program (NCSP)
OPERATION
POWER
POWER PLANTS
PROGRAMMING
REACTIVITY
REACTOR FUELING
REACTORS
SODIUM
SRE
VARIATIONS