NESC0245 RTS.
RTS, Non-Equilibrium Reactor Kinetics in Delayed Neutron Regime
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, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| RTS | NESC0245/01 | Tested | 01-JUL-1964 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NESC0245/01 | IBM 7090 | IBM 7090 |
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3. NATURE OF PHYSICAL PROBLEM SOLVED
RTS solves the reactor kinetic equations in the delay-neutron regime by means of direct numerical evaluation of transient behaviour. It solves the general non- equilibrium kinetics problem with arbitrary reactivity variation and extraneous sources, the customary equilibrium solution being a special case of the general solution.
RTS solves the reactor kinetic equations in the delay-neutron regime by means of direct numerical evaluation of transient behaviour. It solves the general non- equilibrium kinetics problem with arbitrary reactivity variation and extraneous sources, the customary equilibrium solution being a special case of the general solution.
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4. METHOD OF SOLUTION
The reactor kinetic equations are reduced to an integral form convenient for explicit numerical solution, involving no approximations beyond the usual space-independent assumption. RTS performs the numerical evaluation. The characteristic roots and residues which arise in this method of solution have been tabulated for each of the main fissile species. Analytic or point-function reactivity variation may be introduced, together with constant or time-varying reactivity compensation, and the resulting neutron density or power response, total energy release, and compensated reactivity computed as time-dependent functions.
The reactor kinetic equations are reduced to an integral form convenient for explicit numerical solution, involving no approximations beyond the usual space-independent assumption. RTS performs the numerical evaluation. The characteristic roots and residues which arise in this method of solution have been tabulated for each of the main fissile species. Analytic or point-function reactivity variation may be introduced, together with constant or time-varying reactivity compensation, and the resulting neutron density or power response, total energy release, and compensated reactivity computed as time-dependent functions.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
When input reactivity cannot be readily expressed analytically, it may be expressed numerically as a point function of time. The programme as presently written can accommodate in a single run up to 500 data points, which need not be equally spaced in time.
When input reactivity cannot be readily expressed analytically, it may be expressed numerically as a point function of time. The programme as presently written can accommodate in a single run up to 500 data points, which need not be equally spaced in time.
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6. TYPICAL RUNNING TIME
Approximately 1500 integrations per minute for constant time intervals, approximately 10 minutes per curve for uncompensated problems, approximately 30 minutes per curve for compensate problems, on the IBM 704. Typical running times on the IBM 7094 are approximately an order of magnitude faster.
Approximately 1500 integrations per minute for constant time intervals, approximately 10 minutes per curve for uncompensated problems, approximately 30 minutes per curve for compensate problems, on the IBM 704. Typical running times on the IBM 7094 are approximately an order of magnitude faster.
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7. UNUSUAL FEATURES OF THE PROGRAM
Complete output and input dumps available for problem continuation as required. If more than 500 data points are required to specify input reactivity, the problem can be continued by employing a stop-start feature, whereby sets of data points are treated in sequence. Print out flexibility as described in references.
Complete output and input dumps available for problem continuation as required. If more than 500 data points are required to specify input reactivity, the problem can be continued by employing a stop-start feature, whereby sets of data points are treated in sequence. Print out flexibility as described in references.
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10. REFERENCES
- G.R. Keepin and C.W. Cox:
General Solution of the Reactor Kinetic Equations.
Nuclear Science and Engineering, Vol.8, No. 6, December 1960.
- Reactor Kinetics and Control.
AEC Symposium Series Number 2. USAEC Division of Technical Information, 1964
- The Technology of Nuclear Reactor Safety, Vol. 1, Reactor Physics and Control.
The Mit Press, Cambridge MA, 1964
- G.R. Keepin:
Physics of Nuclear Kinetics.
Addison Wesley, Reading MA, 1965
- G.R. Keepin and C.W. Cox:
General Solution of the Reactor Kinetic Equations.
Nuclear Science and Engineering, Vol.8, No. 6, December 1960.
- Reactor Kinetics and Control.
AEC Symposium Series Number 2. USAEC Division of Technical Information, 1964
- The Technology of Nuclear Reactor Safety, Vol. 1, Reactor Physics and Control.
The Mit Press, Cambridge MA, 1964
- G.R. Keepin:
Physics of Nuclear Kinetics.
Addison Wesley, Reading MA, 1965
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NESC0245/01
| File name | File description | Records |
|---|---|---|
| NESC0245_01.001 | SOURCE & DATA FORTRAN 4 | 659 |
| NESC0245_01.002 | OUTPUT FORTRAN 4 | 1128 |
Keywords: delayed neutrons, reactivity, reactor kinetics, transients.