NEA-0492 KAMCCO.
KAMCCO, 3-D Time-Dependent Homogeneous and Inhomogeneous Neutron Transport by Monte-Carlo Method
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 OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| KAMCCO | NEA-0492/02 | Tested | 01-FEB-1978 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-0492/02 | IBM 370 series | IBM 370 series |
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3. NATURE OF PHYSICAL PROBLEM SOLVED
KAMCCO is a 3-dimensional reactor Monte Carlo code for fast neutron physics problems. It includes time dependence and a continuous treatment of the energy. The geometry must be defined in terms of surfaces up to second order. Two options are available:
(a) Census time scheme for time dependent inhomogeneous neutron transport problems.
(b) Source iteration for static eigenfunction problems.
Neutron collisions are treated on a per isotope basis. Elastic scattering retains first order anisotropy in the center-of-mass system. Inelastic scattering is processed via the evaporation model or via the excitation of discrete levels, depending on the pre- collision energy. For fission neutrons an isotope dependent Cranberg spectrum is used. Cross sections are computed in great detail, by linear interpolation, from optionally Doppler broadened single level Breit-Wigner resonances or from probability tables.(see ref.2). Such tables are used in the energy region of narrowly spaced resonances for interpolation in energy and temperature.
KAMCCO is a 3-dimensional reactor Monte Carlo code for fast neutron physics problems. It includes time dependence and a continuous treatment of the energy. The geometry must be defined in terms of surfaces up to second order. Two options are available:
(a) Census time scheme for time dependent inhomogeneous neutron transport problems.
(b) Source iteration for static eigenfunction problems.
Neutron collisions are treated on a per isotope basis. Elastic scattering retains first order anisotropy in the center-of-mass system. Inelastic scattering is processed via the evaporation model or via the excitation of discrete levels, depending on the pre- collision energy. For fission neutrons an isotope dependent Cranberg spectrum is used. Cross sections are computed in great detail, by linear interpolation, from optionally Doppler broadened single level Breit-Wigner resonances or from probability tables.(see ref.2). Such tables are used in the energy region of narrowly spaced resonances for interpolation in energy and temperature.
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4. METHOD OF SOLUTION
The Monte Carlo techniques are mostly analogous. Importance sampling is involved in the collision physics. Leakage estimates may be improved by the MELP/ELP technique (see ref.3). Russian roulette and splitting are employed to a minor extent.
Estimates are obtained from the collision, the track length estimator and their linear combination. Eigenfunction problems are handled by a variant of the power method.
The Monte Carlo techniques are mostly analogous. Importance sampling is involved in the collision physics. Leakage estimates may be improved by the MELP/ELP technique (see ref.3). Russian roulette and splitting are employed to a minor extent.
Estimates are obtained from the collision, the track length estimator and their linear combination. Eigenfunction problems are handled by a variant of the power method.
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7. UNUSUAL FEATURES OF THE PROGRAM
KAMCCO is especially adapted to time dependent problems. As no multigroup or effective cross section formalisms are involved, problems showing both heterogeneity and resonance self-shielding can be handled. The user defines the desired output, e.g. estimates of reaction rates or flux integrated over specified volumes in phase space and time intervals. Such primary quantities can be arbitrarily combined, also ratios of these quantities can be estimated with their errors (see ref.4).
KAMCCO is especially adapted to time dependent problems. As no multigroup or effective cross section formalisms are involved, problems showing both heterogeneity and resonance self-shielding can be handled. The user defines the desired output, e.g. estimates of reaction rates or flux integrated over specified volumes in phase space and time intervals. Such primary quantities can be arbitrarily combined, also ratios of these quantities can be estimated with their errors (see ref.4).
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8. RELATED AND AUXILIARY PROGRAMS
KAMCCO uses nuclear data sets in a special format, prepared by the codes DASU, DISTRESS and DACONT.
DASU uses the KEDAK file (see ref.5) as its main input, DISTRESS generates probability tables by a resonance Ladder method, and DACONT merges and edits their outputs.
KAMCCO uses nuclear data sets in a special format, prepared by the codes DASU, DISTRESS and DACONT.
DASU uses the KEDAK file (see ref.5) as its main input, DISTRESS generates probability tables by a resonance Ladder method, and DACONT merges and edits their outputs.
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10. REFERENCES
- G. Arnecke et al.:
'Efficient Data Management Techniques Implemented in the Karlsruhe Monte Carlo Code KAMCCO'
NEA-CRP-L-118 (= ANL-75-2), p. 5-17 (1974).
- H. Borgwaldt:
'Comparison of 3 Methods to Control the Leakage of Particles in a Monte Carlo Game'
KFK 1391 (1971).
- V. Brandl:
'Die Monte-Carlo-berechnung von Quotienten in der Reaktorphysik'
KFK 2074 (1975).
- B. Hinkelmann et al.:
'Status of the Karlsruhe Evaluated Nuclear Data File KEDAK in June 1970'
KFK 1340 (1971).
- G. Arnecke et al.:
'Efficient Data Management Techniques Implemented in the Karlsruhe Monte Carlo Code KAMCCO'
NEA-CRP-L-118 (= ANL-75-2), p. 5-17 (1974).
- H. Borgwaldt:
'Comparison of 3 Methods to Control the Leakage of Particles in a Monte Carlo Game'
KFK 1391 (1971).
- V. Brandl:
'Die Monte-Carlo-berechnung von Quotienten in der Reaktorphysik'
KFK 2074 (1975).
- B. Hinkelmann et al.:
'Status of the Karlsruhe Evaluated Nuclear Data File KEDAK in June 1970'
KFK 1340 (1971).
NEA-0492/02, included references:
- G. Arnecke, H.Borgwaldt, V.Brandel and M.Lalovic,"KAMCCO, A Reactor Physics Monte Carlo Neutron Transport
Code," (documented by V.Brandl)
KFK-2190 (1975)
- G.Arnecke, H.Borgwaldt, V.Brandel and M.Lalovic,
"KAMCCO, ein reaktorphysikalischer Monte Carlo
Neutronentransportcode"
KFK-2190 (June 1976) In German.
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NEA-0492/02
source program mag tape SRCTPtest-case data mag tape DATTP
test-case output mag tape OUTTP
report REPPT
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- F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics
Keywords: Doppler broadening, KEDAK, Monte Carlo method, anisotropy, cross sections, elastic scattering, fast neutrons, inelastic scattering, neutron transport theory, three-dimensional, time dependence.