LSL-M2: a computer program for least-squares logarithmic adjustment of neutron spectra
Technical Report
·
OSTI ID:5917608
LSL-M2 is a package of computer programs for the adjustment of neutron spectra in nuclear reactors based on the combination of neutron transport calculations and radiometric or other integral dosimetry measurements and their uncertainties in the form of variances and correlations. The underlying algorithm is a least squares logarithmic statistical estimation procedure. Spectra at several different locations can be processed simultaneously which increases the accuracy of the adjusted values and allows the adjustment of spectra at locations without dosimetry. The primary output is adjusted damage parameter values (e.g., fluence > 1.0 MeV and dpa) with uncertainties. The code is written in standard FORTRAN-77 and has been tested for the DEC-10 and the IBM-PC/AT. Requests for the computer code and associated data files should be made through A. Taboada, US Nuclear Regulatory Commission, Mail Code NL 5650, Washington, DC 20555. 15 refs.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5917608
- Report Number(s):
- NUREG/CR-4349; ORNL/TM-9933; ON: TI86008413
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
CROSS SECTIONS
DAMAGING NEUTRON FLUENCE
DOCUMENT TYPES
DOCUMENTATION
MANUALS
MATHEMATICAL MODELS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUENCE
NEUTRON SPECTRA
NEUTRON TRANSPORT
RADIATION EFFECTS
RADIATION TRANSPORT
REACTOR COMPONENTS
SPECTRA
220100* -- Nuclear Reactor Technology-- Theory & Calculation
CROSS SECTIONS
DAMAGING NEUTRON FLUENCE
DOCUMENT TYPES
DOCUMENTATION
MANUALS
MATHEMATICAL MODELS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUENCE
NEUTRON SPECTRA
NEUTRON TRANSPORT
RADIATION EFFECTS
RADIATION TRANSPORT
REACTOR COMPONENTS
SPECTRA