Advances in High Temperature Gas Cooled Reactor Fuel Technology

Advances in High Temperature Gas Cooled Reactor Fuel Technology
Author: International Atomic Energy Agency
Publisher:
Total Pages: 639
Release: 2012-06
Genre: Business & Economics
ISBN: 9789201253101

This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.

The EBR-II Fuel Cycle Story

The EBR-II Fuel Cycle Story
Author: Charles E. Stevenson
Publisher:
Total Pages: 274
Release: 1987
Genre: Technology & Engineering
ISBN:

In this comprehensive volume, Stevenson recounts the history of the Experimental Breeder Reactor-II (EBR-II), the Fuel Cycle Facility (FCF), and the process requirements of this unique technology. The author also explains the reasons behind the remarkable success of both the EBR-II and the FCF. These data, presented as a useful information source, should be of considerable significance to the continuing development of nuclear power.

Electrometallurgical Techniques for DOE Spent Fuel Treatment

Electrometallurgical Techniques for DOE Spent Fuel Treatment
Author: National Research Council
Publisher: National Academies Press
Total Pages: 128
Release: 2000-08-11
Genre: Science
ISBN: 0309070953

The Committee on Electrometallurgical Techniques for DOE Spent Fuel Treatment was formed in September 1994 in response to a request made to the National Research Council (NRC) by the U.S. Department of Energy DOE. DOE requested an evaluation of electrometallurgical processing technology proposed by Argonne National Laboratory (ANL) for the treatment of DOE spent nuclear fuel. Electrometallurgical treatment of spent reactor fuel involves a set of operations designed to remove the remaining uranium metal and to incorporate the radioactive nuclides into well defined and reproducible waste streams. Over the course of the committee's operating life, this charge has remained constant. Within the framework of this overall charge, the scope of the committee's workâ€"as defined by its statement of taskâ€"has evolved in response to further requests from DOE, as well as technical accomplishments and regulatory and legal considerations. As part of its task, the committee has provided periodic assessments of ANL's R&D program on the electrometallurgical technology. Electrometallurgical Techniques for DOE Spent Fuel Treatment assesses the viability of electrometallurgical technology for treating DOE spent nuclear fuel and monitors the scientific and technical progress of the ANL program on electrometallurgical technology, specifically within the context of ANL's demonstration project on electrometallurgical treatment of EBR-II SNF. This report evaluates ANL's performance relative to the success criteria for the demonstration project, which have served as the basis for judging the efficacy of using electrometallurgical technology for the treatment of EBR-II spent nuclear fuel. It also addresses post-demonstration activities related to ANL's electrometallurgical demonstration project, and makes related recommendations in this area.

Safety Related Issues of Spent Nuclear Fuel Storage

Safety Related Issues of Spent Nuclear Fuel Storage
Author: North Atlantic Treaty Organization. Public Diplomacy Division
Publisher: Springer Science & Business Media
Total Pages: 357
Release: 2007-05-09
Genre: Science
ISBN: 1402059019

This book contains papers from a NATO-sponsored workshop in Almaty in September 2005, which discussed safety-related issues of storing spent nuclear fuel. Fifteen papers cover aluminum-clad fuel discharged from research reactors worldwide, while five papers examine stainless steel-clad fuel from fast reactors, and two Zircaloy-clad fuel from commercial light-water reactors.

Comprehensive Nuclear Materials

Comprehensive Nuclear Materials
Author: Todd R Allen
Publisher: Elsevier
Total Pages: 3552
Release: 2011-05-12
Genre: Technology & Engineering
ISBN: 0080560334

Comprehensive Nuclear Materials, Five Volume Set discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials. The work addresses the full panorama of contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environment Fully integrated with F-elements.net, a proprietary database containing useful cross-referenced property data on the lanthanides and actinides Details contemporary developments in numerical simulation, modelling, experimentation, and computational analysis, for effective implementation in labs and plants