Abstract
The adjustment of neutron-fluence spectra at dosimetry surveillance and vessel positions and of the neutron cross sections (parameters) used to calculate them may be carried out in separate steps, provided the dosimetry and the neutron-transport parameters can be appropriately partitioned. We present the prescriptions for carrying out these steps. The purpose is to allow the use of widely available least-squares adjustment codes as modules of a consistent and comprehensive package for the adjustment of all relevant quantities in reactor dosimetry analyses.
| Original language | English |
|---|---|
| Title of host publication | Reactor Dosimetry in the 21st Century |
| Place of Publication | Singapore |
| Publisher | World Scientific Publishing |
| Pages | 415 - 22 |
| Number of pages | 8 |
| State | Published - 2003 |
Bibliographical note
three-stage adjustment;neutron-fluence spectra;dosimetry surveillance;reactor vessel position;neutron cross section parameter;neutron-transport parameter;least-squares adjustment code;comprehensive package;reactor dosimetry analysis;damage parameter;Keywords
- dosimetry
- fission reactor kinetics
- fission reactor materials
- neutron effects
- neutron transport theory
- nuclear engineering computing