Three-stage adjustment of fluences, transport parameters and damage parameters in reactor vessels

J.J. Wagschal, Y. Yeivin, J.G. Williams

Research output: Chapter in Book/Report/Conference proceedingConference contribution


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 languageEnglish
Title of host publicationReactor Dosimetry in the 21st Century
Place of PublicationSingapore
PublisherWorld Scientific Publishing
Pages415 - 22
Number of pages8
StatePublished - 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;


  • dosimetry
  • fission reactor kinetics
  • fission reactor materials
  • neutron effects
  • neutron transport theory
  • nuclear engineering computing


Dive into the research topics of 'Three-stage adjustment of fluences, transport parameters and damage parameters in reactor vessels'. Together they form a unique fingerprint.

Cite this