Varied applications of a new maximum-likelihood code with complete covariance capability. [FERRET, for data adjustment] [electronic resource].
- Published:
- Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1978.
- Physical Description:
- Pages: 18 : digital, PDF file
- Additional Creators:
- United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Summary:
- Applications of a new data-adjustment code are given. The method is based on a maximum-likelihood extension of generalized least-squares methods that allow complete covariance descriptions for the input data and the final adjusted data evaluations. The maximum-likelihood approach is used with a generalized log-normal distribution that provides a way to treat problems with large uncertainties and that circumvents the problem of negative values that can occur for physically positive quantities. The computer code, FERRET, is written to enable the user to apply it to a large variety of problems by modifying only the input subroutine. The following applications are discussed: A 75-group a priori damage function is adjusted by as much as a factor of two by use of 14 integral measurements in different reactor spectra. Reactor spectra and dosimeter cross sections are simultaneously adjusted on the basis of both integral measurements and experimental proton-recoil spectra. The simultaneous use of measured reaction rates, measured worths, microscopic measurements, and theoretical models are used to evaluate dosimeter and fission-product cross sections. Applications in the data reduction of neutron cross section measurements and in the evaluation of reactor after-heat are also considered. 6 figures.
- Report Numbers:
- E 1.99:hedl-sa-1616-fp
E 1.99: conf-780858-9
conf-780858-9
hedl-sa-1616-fp - Subject(s):
- Other Subject(s):
- Data Processing
- Maximum-Likelihood Fit
- Deuteron Reactions
- Direct Reactions
- Lithium 7 Target
- Neutron Reactions
- Capture
- Reactor Kinetics
- Scandium 45 Target
- Silver 109 Target
- Spectra Unfolding
- Computer Calculations
- Cross Sections
- Damaging Neutron Fluence
- Fast Neutrons
- Gamma Radiation
- Kev Range
- Neutron Dosimetry
- Neutron Flux
- Neutrons
- Baryon Reactions
- Baryons
- Charged-Particle Reactions
- Dosimetry
- Electromagnetic Radiation
- Elementary Particles
- Energy Range
- Fermions
- Hadron Reactions
- Hadrons
- Ionizing Radiations
- Kinetics
- Neutron Fluence
- Nuclear Reactions
- Nucleon Reactions
- Nucleons
- Numerical Solution
- Processing
- Radiation Flux
- Radiations
- Targets
- Note:
- Published through SciTech Connect.
01/01/1978.
"hedl-sa-1616-fp"
" conf-780858-9"
Workshop on theory and application of sensitivity and uncertainty analysis, Oak Ridge, TN, USA, 22 Aug 1978.
Schmittroth, F.
Hanford Engineering Development Lab., Richland, WA (USA) - Funding Information:
- EY-76-C-14-2170
View MARC record | catkey: 14372713