Statistical Methods Handbook for Advanced Gas Reactor Fuel Materials

Einerson, J. J.

Idaho National Laboratory

关键词: Manuals;    Advanced Gas Reactor Fuel Materials;    11 - Nuclear Fuel Cycle And Fuel Materials , 21 - Specific Nuclear Reactors And Associated Plants;    Kernels;    Specifications Advanced Gas Reactor Fuel Materials;   

DOI  :  10.2172/911038
RP-ID  :  INL/EXT-05-00349
RP-ID  :  DE-AC07-99ID-13727
RP-ID  :  911038

美国|英语

来源: UNT Digital Library

【 摘 要 】

Fuel materials such as kernels, coated particles, and compacts are being manufactured for experiments simulating service in the next generation of high temperature gas reactors. These must meet predefined acceptance specifications. Many tests are performed for quality assurance, and many of these correspond to criteria that must be met with specified confidence, based on random samples. This report describes the statistical methods to be used. The properties of the tests are discussed, including the risk of false acceptance, the risk of false rejection, and the assumption of normality. Methods for calculating sample sizes are also described.