In the 1980s a series of the Haut Taux de Combustion (HTC) critical experiments with fuel pins in a water-moderated lattice was conducted at the Apparatus B experimental facility in Valduc (Commissariat à l'Energie Atomique, France) with the support of the Institut de Radioprotection et de Sûreté Nucléaire and AREVA NC. Four series of experiments were designed to assess profit associated with actinide-only burnup credit in the criticality safety evaluation for fuel handling, pool storage, and spent-fuel cask conditions.

Optimization of energy resources suggests increased fuel residence in reactor cores and hence improved
fission product evaluations are required. For thermal reactors the fission product cross sections in the JEF2.2 and
JEFF3.1 libraries plus new evaluations from WPEC23 are assessed through modelling the CERES experiment in
the DIMPLE reactor. The analysis uses the lattice code WIMS10. Cross sections for 12 nuclides are assessed. The
thermal cross section and low energy resonance data for 147,152Sm and 155Gd are accurate to within 4%. Similar data

Target accuracy on LWR neutronics parameters is 2 to 5 times lower than the a priori uncertainty (1σ)
due to nuclear data. This paper summarizes the experimental facilities and the integral measurements that are required
for code qualification. The rigorous use of integral information through trend analysis method is described. Trends
on JEF2 data from Keff measurements and P.I.Es are presented. These trends were accounted for in the new JEFF3
evaluations. The role of fundamental experiments, such as worth measurement of separated isotopes, is emphasized.

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.

The voluntary siting process for the Monitored Retrievable Storage (MRS) facility set forth in the Nuclear Waste Policy Amendments Act (NWPAA) of 1987 provides a potential host community a unique opportunity to improve its present situation and to gain greater control over its future.

<p>A report from the US&nbsp; Deparement of Energy&#39;s Office of Civilian Radioactive Waste Management</p>

<p>Regulatory Drop Tests Planned for a Model Transportation Cask</p>

<p>Implementation Plan for the environmental Impact Statement for a Multi-Purpose Canister System for Management of Civilian and Naval Spent Nuclear Fuel Issued</p>

<p>Nuclear Waste Technical Review Board (NWTRB) Update</p>

<p>The NWTRB</p>

<p>Dry Transfer System Design Under Way</p>

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

<p>Highlights Include....</p>

<p>OCRWM FY 1996 Budget Presented to Congress</p>

<p>Public Responds to Waste Acceptance Issues</p>

<p>Transportation External Coordination Working Group Convenes in North Carolina</p>

<p>OCRWM Completes Draft Public Participation Plan</p>

<p>International Program Update</p>

<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>

<p>MULTI-PURPOSE CANISTER PROCUREMENT: A SIGNIFICANT STEP FOR THE DEPARTMENT OF ENERGY&#39;S CIVILIAN RADIOACTIVE WASTE MANAGEMENT PROGRAM</p>

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

<p>Highlights include...</p>

<p>Westinghouse begins designing multi-purpose canister</p>

<p>DOE accepts General Atomics-9 assembly transportation cask trailer</p>

<p>Final interpretation of nuclear waste acceptance issues published</p>

In 1999, the United States Nuclear Regulatory Commission (U.S. NRC) initiated a research program
to support the development of technical bases and guidance that would facilitate the implementation of burnup
credit into licensing activities for transport and dry cask storage. This paper reviews the following major areas of
investigation: (1) specification of axial burnup profiles, (2) assumption on cooling time, (3) allowance for
assemblies with fixed and removable neutron absorbers, (4) the need for a burnup margin for fuel with initial

WASHINGTON, D.C. (April 28, 2016) – Waste Control Specialists LLC (WCS) submitted an application to the Nuclear Regulatory Commission (NRC) for a license to construct and operate a Consolidated Interim Storage Facility (CISF) for used nuclear fuel. The filing comes after a year of pre-application meetings with NRC and maintains the timeline WCS outlined in February 2015.

The application is being led by WCS, along with its partners AREVA and NAC International, both global industry leaders in the transportation and storage of used nuclear fuel.

Conference papers on the IWM Execution Strategy Analysis process and tool.