Users manual for the FORSS sensitivity and uncertainty analysis code system

Abstract

FORSS is a code system used to study relationships between nuclear reaction cross sections, integral experiments, reactor performance parameter predictions and associated uncertainties. This report describes the computing environment and the modules currently used to implement FORSS Sensitivity and Uncertainty Methodology.

Keywords

SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
GENERAL STUDIES OF NUCLEAR REACTORS
COMPUTER CODES
F CODES
FAST REACTORS
REACTOR PHYSICS
COMPUTER CALCULATIONS
CROSS SECTIONS
MANUALS
SENSITIVITY
DOCUMENT TYPES
EPITHERMAL REACTORS
PHYSICS
REACTORS 210500* -- POWER REACTORS
BREEDING
-- NUCLEAR REACTOR TECHNOLOGY-- THEORY & CALCULATION

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