Computer Programs

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, 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 UNDER WHICH PROGRAM IS EXECUTED, 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 |
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SENSIT | CCC-0405/01 | Tested | 21-SEP-1981 |

Machines used:

Package ID | Orig. computer | Test computer |
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CCC-0405/01 | IBM 3033 | IBM 3033 |

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3. DESCRIPTION OF PROBLEM OR FUNCTION

SENSIT computes the sensitivity and uncertainty of a calculated integral response (such as a dose rate) due to input cross sections and their uncertainties.

Sensitivity profiles are computed for neutron and gamma-ray reaction cross sections (of standard multigroup cross-section sets) and for secondary energy distributions (SED's) of multigroup scattering matrices. In the design sensitivity mode, SENSIT computes changes in an integral response due to design changes and gives the appropriate sensitivity coefficients. Cross-section uncertainty analyses are performed for three types of input data uncertainties:

(a) cross-section covariance matrices for pairs of multigroup reaction cross sections, (b) spectral shape uncertainty parameters for secondary energy distributions (integral SED uncertainties), and (c) covariance matrices for energy-dependent response functions.

SENSIT computes the sensitivity and uncertainty of a calculated integral response (such as a dose rate) due to input cross sections and their uncertainties.

Sensitivity profiles are computed for neutron and gamma-ray reaction cross sections (of standard multigroup cross-section sets) and for secondary energy distributions (SED's) of multigroup scattering matrices. In the design sensitivity mode, SENSIT computes changes in an integral response due to design changes and gives the appropriate sensitivity coefficients. Cross-section uncertainty analyses are performed for three types of input data uncertainties:

(a) cross-section covariance matrices for pairs of multigroup reaction cross sections, (b) spectral shape uncertainty parameters for secondary energy distributions (integral SED uncertainties), and (c) covariance matrices for energy-dependent response functions.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

SENSIT uses one-, two-, and three dimensional arrays to manage the large amount of numerical data involved in the execution. Core storage is reserved for a particular dimensional array only during the time the corresponding data are required to be in-core; at other times, the space is made available for the storage of other data. In order to alleviate bookkeeping chores associated with such dynamic storage allocation techniques, Argonne National Laboratory developed a collection of subroutines, called the BPOINTR package, which is incorporated in SENSIT.

SENSIT uses one-, two-, and three dimensional arrays to manage the large amount of numerical data involved in the execution. Core storage is reserved for a particular dimensional array only during the time the corresponding data are required to be in-core; at other times, the space is made available for the storage of other data. In order to alleviate bookkeeping chores associated with such dynamic storage allocation techniques, Argonne National Laboratory developed a collection of subroutines, called the BPOINTR package, which is incorporated in SENSIT.

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6. TYPICAL RUNNING TIME

A typical execution time on the CDC-7600 for a standard cross-section sensitivity analysis, together with an SED uncertainty analysis is about 4 seconds CPU (central processor units) time. Here a coupled neutron/gamma group structure of 30 x 12 groups, P3 cross-sections, and 137 spatial intervals was used. A typical vector cross-section sensitivity and uncertainty analysis with 30 x 30 covariance matrices requires about 2 seconds of CPU time per case.

A typical execution time on the CDC-7600 for a standard cross-section sensitivity analysis, together with an SED uncertainty analysis is about 4 seconds CPU (central processor units) time. Here a coupled neutron/gamma group structure of 30 x 12 groups, P3 cross-sections, and 137 spatial intervals was used. A typical vector cross-section sensitivity and uncertainty analysis with 30 x 30 covariance matrices requires about 2 seconds of CPU time per case.

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8. RELATED AND AUXILIARY PROGRAMS

SENSIT uses angular-flux files from one-dimensional discrete-ordinates codes like ONETRAN, ANISN and DTF and reads multigroup cross-section sets in three different formats. For covariance data input a convenient ENDF-like input format is adopted which is identical to the output format from the cross- section processing code system NJOY.

SENSIT uses angular-flux files from one-dimensional discrete-ordinates codes like ONETRAN, ANISN and DTF and reads multigroup cross-section sets in three different formats. For covariance data input a convenient ENDF-like input format is adopted which is identical to the output format from the cross- section processing code system NJOY.

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10. REFERENCES

- S.A.W. Gerstl, R.J. LaBauve, and P.G. Young:

"A Comprehensive Neutron Cross-Section and Secondary Energy Dis-

tribution Uncertainty Analysis for a Fusion Reactor",

Los Alamos Scientific Laboratory report LA-8333-MS (May 1980).

- S.A.W. Gerstl, R.J. LaBauve, and P.G. Young:

"A Comprehensive Neutron Cross-Section and Secondary Energy Dis-

tribution Uncertainty Analysis for a Fusion Reactor",

Los Alamos Scientific Laboratory report LA-8333-MS (May 1980).

CCC-0405/01, included references:

- S.A.W. Gerstl:SENSIT: A Cross Section and Design Sensitivity and Uncertainty

Analysis Code

LA-8498-MS UC-32 (August 1980).

- BPOINTER + POINTER Description of Subroutines.

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11. MACHINE REQUIREMENTS

Due to the variable dimensioning as described above, large flexibility exists to adjust the storage requirements for a specific problem to the available machine core. On a CDC-7600 all of the 8 sample problems and the realistic applications could be executed within a maximum of 24000 words of fast (SCM) core and 80000 words of extended-core (ECM) memory.

Due to the variable dimensioning as described above, large flexibility exists to adjust the storage requirements for a specific problem to the available machine core. On a CDC-7600 all of the 8 sample problems and the realistic applications could be executed within a maximum of 24000 words of fast (SCM) core and 80000 words of extended-core (ECM) memory.

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CCC-0405/01

File name | File description | Records |
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CCC0405_01.001 | SENSIT MAIN PROGRAM (F4) | 697 |

CCC0405_01.002 | COMPUTATIONAL SUBROUTINES | 2647 |

CCC0405_01.003 | BPOINTR FORTRAN ROUTINES | 1580 |

CCC0405_01.004 | BPOINTR ASSEMBLER ROUTINES | 314 |

CCC0405_01.005 | ANISN FORWARD SAMPLE PROBLEM | 35 |

CCC0405_01.006 | ANISN ADJOINT SAMPLE PROBLEM | 37 |

CCC0405_01.007 | ANISN OUTPUT FORWARD PROBLEM | 472 |

CCC0405_01.008 | ANISN OUTPUT ADJOINT PROBLEM | 473 |

CCC0405_01.009 | SENSIT S.P. 1 INPUT | 42 |

CCC0405_01.010 | SENSIT S.P. 2 INPUT | 30 |

CCC0405_01.011 | SENSIT S.P. 1 OUTPUT | 330 |

CCC0405_01.012 | SENSIT S.P. 2 OUTPUT | 252 |

CCC0405_01.013 | TAPE4 CROSS SECTION FOR S.P. | 20 |

CCC0405_01.014 | JCL AND INFORMATION | 149 |

Keywords: cross sections, dose rates, gamma radiation, multigroup, neutron reactions, perturbation theory, response functions, sensitivity.