NEA-0157 SPM-046.
SPM-046, Reactor Kinetics by 1 Group Diffusion Calculation in R-Z Geometry
NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, AUXILIARIES, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| SPM-046 | NEA-0157/01 | Tested | 01-MAR-1965 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-0157/01 | IBM 7094 | IBM 7094 |
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3. NATURE OF PHYSICAL PROBLEM SOLVED
The time dependent diffusion equation in one neutron group is integrated for a reactor in r-z geometry. Transients due to axial movement of absorbers, or variation in coolant flow, can be studied. The model can be controlled to maintain a constant mean flux in the whole reactor, or to preserve axial flux distributions in three regions. Account is taken of the reactivity effects of temperature variation in fuel and moderator, and xenon poisoning.
Control is by axial movement of absorber situated anywhere in the reactor.
The time dependent diffusion equation in one neutron group is integrated for a reactor in r-z geometry. Transients due to axial movement of absorbers, or variation in coolant flow, can be studied. The model can be controlled to maintain a constant mean flux in the whole reactor, or to preserve axial flux distributions in three regions. Account is taken of the reactivity effects of temperature variation in fuel and moderator, and xenon poisoning.
Control is by axial movement of absorber situated anywhere in the reactor.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
One to six delayed neutron groups. Five temperatures - fuel, canning, coolant, surface of moderator and bulk moderator. A maximum of 20 x 30 mesh points can be accommodated. Radial and axial reflectors are simulated by extrapolation conditions. The thermal characteristics are assumed uniform with the exception of the coolant for which the radial distribution is estimated, assuming that the exit temperature is constant, and taking proper account of the thermal capacity of the moderator.
Overall control is a function of the temperature variation of the coolant at exit. The axial control is a function of the variation of the relation between the heating of the canning and the heating of the coolant.
One to six delayed neutron groups. Five temperatures - fuel, canning, coolant, surface of moderator and bulk moderator. A maximum of 20 x 30 mesh points can be accommodated. Radial and axial reflectors are simulated by extrapolation conditions. The thermal characteristics are assumed uniform with the exception of the coolant for which the radial distribution is estimated, assuming that the exit temperature is constant, and taking proper account of the thermal capacity of the moderator.
Overall control is a function of the temperature variation of the coolant at exit. The axial control is a function of the variation of the relation between the heating of the canning and the heating of the coolant.
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NEA-0157/01
| File name | File description | Records |
|---|---|---|
| NEA0157_01.001 | SOURCE & DATA | 1836 |
| NEA0157_01.002 | OUTPUT | 431 |
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- F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics
Keywords: absorption, coolants, finite difference method, moderators, neutron diffusion equation, poisoning, r-z, temperature, time dependence, transients.