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SENSIT: a cross-section and design sensitivity and uncertainty analysis code. [In FORTRAN for CDC-7600, IBM 360]

Conference ·
OSTI ID:7093344

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 (SEDs) 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: cross-section covariance matrices for pairs of multigroup reaction cross sections, spectral shape uncertainty parameters for secondary energy distributions (integral SED uncertainties), and covariance matrices for energy-dependent response functions. For all three types of data uncertainties SENSIT computes the resulting variance and estimated standard deviation in an integral response of interest, on the basis of generalized perturbation theory. SENSIT attempts to be more comprehensive than earlier sensitivity analysis codes, such as SWANLAKE.

Research Organization:
Los Alamos Scientific Lab., NM (USA)
DOE Contract Number:
W-7405-ENG-36
OSTI ID:
7093344
Report Number(s):
LA-UR-80-2868; CONF-8010113-3
Country of Publication:
United States
Language:
English

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Related Subjects

654001* -- Radiation & Shielding Physics-- Radiation Physics
Shielding Calculations & Experiments
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYON REACTIONS
CDC COMPUTERS
COMPUTER CODES
COMPUTERS
CROSS SECTIONS
DATA COVARIANCES
DOSE RATES
FORTRAN
FUNCTIONS
HADRON REACTIONS
IBM COMPUTERS
MULTIGROUP THEORY
NEUTRON REACTIONS
NEUTRON TRANSPORT THEORY
NUCLEAR REACTIONS
NUCLEON REACTIONS
PHOTONUCLEAR REACTIONS
PROGRAMMING LANGUAGES
RESPONSE FUNCTIONS
S CODES
SENSITIVITY ANALYSIS
TRANSPORT THEORY