The responsible use of calculational methods in nuclear criticality safety includes a determination of bias and bias uncertainty that may exist between the calculated results and reality. Such biases exist due to approximations used to model the real world, uncertainties in nuclear data, and approximations associated with the calculational method (e.g., Monte Carlo method). The bias and bias uncertainty are typically determined by using the modeling approximations, nuclear data, and calculational method to model well-known, usually critical, systems.

This publication records the proceedings of a technical meeting organized by the IAEA and
held in London 29 August–2 September 2005 with sixty participants from 18 countries. As
indicated in the title, the objective of this meeting was to provide a forum for exchange of
technical information on spent fuel burnup credit applications and thereby compile state-ofthe-
art information on technical advances related to spent fuel transportation, storage,
reprocessing and disposition.

<p>A newsletter from the Office of Civilian Radioactive Waste Management</p>

<p>OCRWM Director Briefs US. Nuclear Regulatory Commission .</p>

<p>Notice of Inquiry: Technical Assistance and Training for Safe Transportation of Radioactive Waste</p>

<p>OCRWM Program Plan</p>

<p>Environmental Impact Statement Scoping for the Multi-Purpose&nbsp; Canister-Based System</p>

<p>Nuclear Waste Technical Review Board Update,</p>

<p>Nuclear Wasre Negotiator Update</p>