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Siting Experience Documents Only
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OECD/NEA: Slovak Republic
OECD/NEA: Slovak Republic
OECD/NEA: Spain
OECD/NEA: Spain
OECD/NEA: Korea
OECD/NEA: Korea
OECD/NEA: Sweden
OECD/NEA: Sweden
OECD/NEA: Hungary
OECD/NEA: Hungary
Radioactive Waste Management and Decommissioning in Korea
Radioactive Waste Management and Decommissioning in Korea
OECD/NEA: Finland
OECD/NEA: Finland
OECD/NEA: Netherlands
OECD/NEA: Netherlands
OECD/NEA: France
OECD/NEA: France
OECD/NEA: Czech Republic
OECD/NEA: Czech Republic
OECD/NEA: Mexico
OECD/NEA: Mexico
2008 Activity Report
Tender for Construction of Spanish Waste Store
Tender for Construction of Spanish Waste Store
News article discussing the tender that Spain has issued for the contract to build the main civil works at the planned national high-level waste storage facility in central Spain.
Radioactive Waste Management Programmes in OECD/NEA Member Countries: Germany
Radioactive Waste Management Programmes in OECD/NEA Member Countries: Germany
A summary of the radioactive waste management program in Germany as of 2013, including the national nuclear energy context; sources, types, and quantities of waste; radioactive waste management policies and programs; research and development; decommissioning and dismantling policies and projects; transport; competent authorities; financing; and public information.
The MRS Task Force: Economic and Non-Economic Incentives for Local Public Acceptance of a Proposed Nuclear Waste Packaging and Storage Facility
The MRS Task Force: Economic and Non-Economic Incentives for Local Public Acceptance of a Proposed Nuclear Waste Packaging and Storage Facility
A joint Oak Ridge - Roane County citizen task force (TF) evaluated the<br/>Department of Energy's (DOE) proposal to site a Monitored Retrievable Storage<br/>facility in Tennessee in terms of environmental, transportation and socioeconomic<br/>impacts. The case study examines how the TF used mitigation, compensation and<br/>incentives (economic and non-economic) to address the problem of distrust of DOE<br/>and to change the net local impact balance from negative to positive.
From Integral Experiments to Nuclear Data Improvement
From Integral Experiments to Nuclear Data Improvement
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.
SCALE-4 Analysis of Pressurized Water REactor Critical Configurations: Volume 5 - North Anna Unit 1 Cycle 5
SCALE-4 Analysis of Pressurized Water REactor Critical Configurations: Volume 5 - North Anna Unit 1 Cycle 5
The requirements of ANSI/ANS 8.1 specify that calculational methods for away-from-reactor
(AFR) criticality safety analyses be validated against experimental measurements. If credit for the
negative reactivity of the depleted (or spent) fuel isotopics is desired, it is necessary to benchmark
computational methods against spent fuel critical configurations. This report summarizes a portion
of the ongoing effort to benchmark AFR criticality analysis methods using selected critical
configurations from commercial pressurized-water reactors (PWR).
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs
This paper presents an evaluation of the amount of burnup credit needed for high-density casks to
transport the current U.S. inventory of commercial spent nuclear fuel (SNF) assemblies. A prototypic
32-assembly cask and the current regulatory guidance were used as bases for this evaluation.
By comparing actual pressurized-water-reactor (PWR) discharge data (i.e., fuel burnup and initial
enrichment specifications for fuel assemblies discharged from U.S. PWRs) with actinide-only-based
PWR Axial Burnup Profile Analysis
PWR Axial Burnup Profile Analysis
Monitored Retrievable Storage Project Plan
Monitored Retrievable Storage Project Plan
The purpose of this document is to describe the Monitored Retrievable Storage (MRS) Project and to establish approved cost and schedule baselines against which overall progress and management effectiveness shall be measured. For the sake of brevity, this Project Plan will be referred to as the Plan throughout this document.
DHLW Glass Waste Package Criticality Analysis (SCPB: N/A)
DHLW Glass Waste Package Criticality Analysis (SCPB: N/A)
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to determine the viability of the Defense High-Level Waste (DHLW) Glass waste package concept with respect to criticality regulatory requirements in compliance with the goals of the Waste Package Implementation Plan (Ref. 5.1) for conceptual design. These design calculations are performed in sufficient detail to provide a comprehensive comparison base with other design alternatives.
FEDERAL COMMITMENTS REGARDING USED FUEL AND HIGH-LEVEL WASTES
FEDERAL COMMITMENTS REGARDING USED FUEL AND HIGH-LEVEL WASTES
Criticality Evaluation of Degraded Internal Configurations for a 44 BWR Waste Package
Criticality Evaluation of Degraded Internal Configurations for a 44 BWR Waste Package
The purpose of this calculation is to perform an example criticality evaluation for degraded internal configurations of a boiling water reactor (BWR) waste package (WP) containing 44 spent nuclear fuel (SNF) assemblies.
EQ6 Calculation for Chemical Degradation of Shippingport PWR (HEU Oxide) Spent Nuclear Fuel Waste Packages
EQ6 Calculation for Chemical Degradation of Shippingport PWR (HEU Oxide) Spent Nuclear Fuel Waste Packages
The Monitored Geologic Repository (MGR) Waste Package Operations (WPO) of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Shippingport Pressurized Water Reactor (PWR) (Ref. 1). The Shippingport PWR SNF has been considered for disposal at the proposed Yucca Mountain site.