DOCSLIB.ORG

Background, Status and Issues Related to the Regulation of Advanced Spent Nuclear Fuel Recycle Facilities

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Background, Status and Issues Related to the Regulation of Advanced Spent Nuclear Fuel Recycle Facilities NUREG-1909 Background, Status, and Issues Related to the Regulation of Advanced Spent Nuclear Fuel Recycle Facilities ACNW&M White Paper Advisory Committee on Nuclear Waste and Materials NUREG-1909 Background, Status, and Issues Related to the Regulation of Advanced Spent Nuclear Fuel Recycle Facilities ACNW&M White Paper Manuscript Completed: May 2008 Date Published: June 2008 Prepared by A.G. Croff, R.G. Wymer, L.L. Tavlarides, J.H. Flack, H.G. Larson Advisory Committee on Nuclear Waste and Materials THIS PAGE WAS LEFT BLANK INTENTIONALLY ii ABSTRACT In February 2006, the Commission directed the Advisory Committee on Nuclear Waste and Materials (ACNW&M) to remain abreast of developments in the area of spent nuclear fuel reprocessing, and to be ready to provide advice should the need arise. A white paper was prepared in response to that direction and focuses on three major areas: (1) historical approaches to development, design, and operation of spent nuclear fuel recycle facilities, (2) recent advances in spent nuclear fuel recycle technologies, and (3) technical and regulatory issues that will need to be addressed if advanced spent nuclear fuel recycle is to be implemented. This white paper was sent to the Commission by the ACNW&M as an attachment to a letter dated October 11, 2007 (ML072840119). In addition to being useful to the ACNW&M in advising the Commission, the authors believe that the white paper could be useful to a broad audience, including the NRC staff, the U.S. Department of Energy and its contractors, and other organizations interested in understanding the nuclear fuel cycle. ****** Paperwork Reduction Act Statement This NUREG does not contain information collection requirements and, therefore, is not subject to the requirements of the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number. iii THIS PAGE WAS LEFT BLANK INTENTIONALLY iv TABLE OF CONTENTS ABSTRACT .................................................................................................................................iii EXECUTIVE SUMMARY ............................................................................................................xv INTRODUCTION..................................................................................................................... xv SPENT NUCLEAR FUEL RECYCLE HISTORY AND TECHNOLOGY ................................. xvi What is Reprocessed?....................................................................................................... xvi How is SNF Currently Reprocessed? ................................................................................ xvi Where was and Is SNF Reprocessed? .............................................................................xviii What Is the Status of SNF Reprocessing Technology? ....................................................xviii Where Is Fuel Refabricated? ............................................................................................. xix ADVANCED RECYCLE TECHNOLOGY............................................................................... xix Overview of Advanced Spent Nuclear Fuel Recycle Initiatives.......................................... xix Advanced Fuel Reprocessing Technology......................................................................... xix Advanced Fuel Fabrication and Refabrication ................................................................... xxi REGULATION AND LICENSING OF FUEL RECYCLE FACILITIES .................................... xxi ISSUES ASSOCIATED WITH LICENSING AND REGULATING FUEL RECYCLE FACILITIES............................................................................................................................xxii Development of Licensing Regulation(s) for Recycle Facilities ........................................xxii Impacts of SNF Recycle on Related Regulations .............................................................xxiv Other Regulatory Issues Arising from SNF Recycle ......................................................... xxv RESEARCH NEEDS........................................................................................................... xxviii ACKNOWLEDGEMENTS .......................................................................................................xxix LIST OF ACRONYMS .............................................................................................................xxxi 1. INTRODUCTION...................................................................................................................1 1.1. Background and Context...................................................................................................1 1.2. Goal and Purposes ...........................................................................................................3 1.3. Scope ................................................................................................................................4 1.4. Information Sources ..........................................................................................................5 2. RECYCLE FACILITY FEEDSTOCK: SPENT NUCLEAR FUEL DESIGNS .......................7 2.1. Overview of generic Fuel Cycles.......................................................................................7 2.1.1. Uranium-Plutonium Fuel Cycle..................................................................................7 2.1.2. Thorium-Uranium Fuel Cycle .....................................................................................7 2.2. Fuel Designs .....................................................................................................................7 2.2.1. Pressurized Water Reactors (PWR) .........................................................................7 v 2.2.2. Boiling Water Reactors (BWR)..................................................................................8 2.2.3. Fast Reactors............................................................................................................9 2.2.3.1. Oxide................................................................................................................10 2.2.3.2. Carbide.............................................................................................................10 2.2.3.3. Uranium/Plutonium/Zirconium Metal Alloy .......................................................11 2.2.3.4. Nitride...............................................................................................................11 2.2.4. High-Temperature Gas-Cooled Reactors (HTGR)....................................................12 2.2.5. Molten Salt Reactor (MSR) ......................................................................................12 3. OVERVIEW OF SPENT NUCLEAR FUEL RECYCLE...................................................13 3.1. Reprocessing Experience and Evaluations.....................................................................13 3.1.1. U.S. Defense and Commercial Reprocessing Plants..............................................13 3.1.1.1. Reprocessing for Weapons Plutonium Recovery.............................................13 3.1.1.1.1. Bismuth Phosphate Process .....................................................................13 3.1.1.1.2. Redox Process (Hexone) ..........................................................................14 3.1.1.1.3. PUREX Process........................................................................................15 3.1.1.2. U.S. Commercial Reprocessing Plants ............................................................17 3.1.1.2.1. Nuclear Fuel Services (NFS - West Valley Plant) .....................................17 3.1.1.2.2. GE Morris Plant.........................................................................................17 3.1.1.2.3. Barnwell Nuclear Fuel Plant.....................................................................17 3.1.2. International Reprocessing Plant Summary............................................................17 3.1.2.1. France ..............................................................................................................20 3.1.2.2. Great Britain .....................................................................................................20 3.1.2.3. Japan ...............................................................................................................21 3.1.2.4. Russia ..............................................................................................................21 3.1.2.5. India .................................................................................................................21 3.1.2.6. China................................................................................................................22 3.1.2.7. South Korea .....................................................................................................22 3.1.3 THORP Reprocessing Plant PUREX Process .........................................................23 3.1.3.1. Spent Nuclear Fuel Shearing and Dissolution..................................................24 3.1.3.2. High Activity (HA) Cycle ...................................................................................24 3.1.3.3. Plutonium Purification
Load more

Recommended publications
  • Spent Nuclear Fuel Pools in the US
    Spent Nuclear Fuel Pools in the U.S.: Reducing the Deadly Risks of Storage front cover WITH SUPPORT FROM: WITH SUPPORT FROM: By Robert Alvarez 1112 16th St. NW, Suite 600, Washington DC 20036 - www.ips-dc.org May 2011 About the Author Robert Alvarez, an Institute for Policy Studies senior scholar, served as a Senior Policy Advisor to the Secre- tary of Energy during the Clinton administration. Institute for Policy Studies (IPS-DC.org) is a community of public scholars and organizers linking peace, justice, and the environment in the U.S. and globally. We work with social movements to promote true democracy and challenge concentrated wealth, corporate influence, and military power. Project On Government Oversight (POGO.org) was founded in 1981 as an independent nonprofit that investigates and exposes corruption and other misconduct in order to achieve a more effective, accountable, open, and ethical federal government. Institute for Policy Studies 1112 16th St. NW, Suite 600 Washington, DC 20036 http://www.ips-dc.org © 2011 Institute for Policy Studies [email protected] For additional copies of this report, see www.ips-dc.org Table of Contents Summary ...............................................................................................................................1 Introduction ..........................................................................................................................4 Figure 1: Explosion Sequence at Reactor No. 3 ........................................................4 Figure 2: Reactor No. 3
    [Show full text]
  • Table 2.Iii.1. Fissionable Isotopes1
    FISSIONABLE ISOTOPES Charles P. Blair Last revised: 2012 “While several isotopes are theoretically fissionable, RANNSAD defines fissionable isotopes as either uranium-233 or 235; plutonium 238, 239, 240, 241, or 242, or Americium-241. See, Ackerman, Asal, Bale, Blair and Rethemeyer, Anatomizing Radiological and Nuclear Non-State Adversaries: Identifying the Adversary, p. 99-101, footnote #10, TABLE 2.III.1. FISSIONABLE ISOTOPES1 Isotope Availability Possible Fission Bare Critical Weapon-types mass2 Uranium-233 MEDIUM: DOE reportedly stores Gun-type or implosion-type 15 kg more than one metric ton of U- 233.3 Uranium-235 HIGH: As of 2007, 1700 metric Gun-type or implosion-type 50 kg tons of HEU existed globally, in both civilian and military stocks.4 Plutonium- HIGH: A separated global stock of Implosion 10 kg 238 plutonium, both civilian and military, of over 500 tons.5 Implosion 10 kg Plutonium- Produced in military and civilian 239 reactor fuels. Typically, reactor Plutonium- grade plutonium (RGP) consists Implosion 40 kg 240 of roughly 60 percent plutonium- Plutonium- 239, 25 percent plutonium-240, Implosion 10-13 kg nine percent plutonium-241, five 241 percent plutonium-242 and one Plutonium- percent plutonium-2386 (these Implosion 89 -100 kg 242 percentages are influenced by how long the fuel is irradiated in the reactor).7 1 This table is drawn, in part, from Charles P. Blair, “Jihadists and Nuclear Weapons,” in Gary A. Ackerman and Jeremy Tamsett, ed., Jihadists and Weapons of Mass Destruction: A Growing Threat (New York: Taylor and Francis, 2009), pp. 196-197. See also, David Albright N 2 “Bare critical mass” refers to the absence of an initiator or a reflector.
    [Show full text]
  • The Nuclear Waste Primer September 2016 What Is Nuclear Waste?
    The Nuclear Waste Primer September 2016 What is Nuclear Waste? Nuclear waste is the catch-all term for anything contaminated with radioactive material. Nuclear waste can be broadly divided into three categories: • Low-level waste (LLW), comprised of protective clothing, medical waste, and other lightly-contaminated items • Transuranic waste (TRU), comprised of long-lived isotopes heavier than uranium • High-level waste (HLW), comprised of spent nuclear fuel and other highly-radioactive materials Low-level waste is relatively short-lived and easy to handle. Currently, four locations for LLW disposal exist in the United States. Two of them, Energy Solutions in Clive, Utah and Waste Control Specialists in Andrews, Texas, accept waste from any U.S. state. Transuranic waste is often a byproduct of nuclear weapons production and contains long-lived radioactive elements heavier than uranium, like plutonium and americium. Currently, the U.S. stores TRU waste at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. High-level waste includes spent nuclear fuel and the most radioactive materials produced by nuclear weapons production. Yucca Mountain is the currently designated high-level waste repository for the United States. 1 | What is Spent Nuclear Fuel? Spent nuclear fuel (SNF), alternatively referred to as used nuclear fuel, is the primary byproduct of nuclear reactors. In commercial power reactors in the U.S., fuel begins as uranium oxide clad in a thin layer of zirconium-aluminum cladding. After several years inside of the reactor, around fi ve percent of the uranium has been converted in some way, ranging from short-lived and highly radioactive fi ssion products to long-lived actinides like plutonium, americium, and neptunium.
    [Show full text]
  • Nuclear Transmutation Strategies for Management of Long-Lived Fission
    PRAMANA c Indian Academy of Sciences Vol. 85, No. 3 — journal of September 2015 physics pp. 517–523 Nuclear transmutation strategies for management of long-lived fission products S KAILAS1,2,∗, M HEMALATHA2 and A SAXENA1 1Nuclear Physics Division, Bhabha Atomic Research Centre, Mumbai 400 085, India 2UM–DAE Centre for Excellence in Basic Sciences, Mumbai 400 098, India ∗Corresponding author. E-mail: [email protected] DOI: 10.1007/s12043-015-1063-z; ePublication: 27 August 2015 Abstract. Management of long-lived nuclear waste produced in a reactor is essential for long- term sustenance of nuclear energy programme. A number of strategies are being explored for the effective transmutation of long-lived nuclear waste in general, and long-lived fission products (LLFP), in particular. Some of the options available for the transmutation of LLFP are discussed. Keywords. Nuclear transmutation; long-lived fission products; (n, γ ) cross-section; EMPIRE. PACS Nos 28.41.Kw; 25.40.Fq; 24.60.Dr 1. Introduction It is recognized that for long-term energy security, nuclear energy is an inevitable option [1]. For a sustainable nuclear energy programme, the management of long-lived nuclear waste is very critical. Radioactive nuclei like Pu, minor actinides like Np, Am and Cm and long-lived fission products like 79Se, 93Zr, 99Tc, 107Pd, 126Sn, 129I and 135Cs constitute the main waste burden from a power reactor. In this paper, we shall discuss the management strategies for nuclear waste in general, and long-lived fission products, in particular. 2. Management of nuclear waste The radioactive nuclei which are produced in a power reactor and which remain in the spent fuel of the reactor form a major portion of nuclear waste.
    [Show full text]
  • Security of Supply of Medical Radioisotopes - a Clinical View Dr Beverley Ellis Consultant Radiopharmacist
    Security of Supply of Medical Radioisotopes - a clinical view Dr Beverley Ellis Consultant Radiopharmacist Nuclear Medicine Centre Manchester University NHS Foundation Trust Nuclear Medicine § Approx 35 million clinical radionuclide imaging procedures worldwide § Globally 2nd most common imaging technique after CT (higher than MR) 20 million in USA 9 million in Europe 3 million in Japan 3 million in rest of the world Approx 700, 000 nuclear medicine procedures per year in UK Myocardial Perfusion - Ischaemia Stress Stress SA Rest Stress VLA Rest Stress HLA Rest Rest Tc-99m Bone Scans Normal Metastases Mo-99/Tc-99m Generator Supply Tc-99m Radiopharmaceutical Production Mo-99 Shortages Design of Clinical Services to Reduce Tc-99m Use § Optimisation of generator management – Efficiency savings – Delivery and extraction schedules – Patient scheduling § Improved communication – Customers – Suppliers § Improved software – gamma cameras – Produce comparable quality images using less radioactivity Global Situation § OECD/Nuclear Energy Agency (NEA) – Set up High Level Group (HLG-MR) in 2009 – Security of supply of Mo-99 and Tc-99m – Established 6 principles e.g. full cost recovery and outage reserve capacity – Issued a series of publications Global Situation § AIPES (Association of Imaging Producers & Equipment supplies) (Now called Nuclear Medicine Europe) – Support coordination of research reactor schedules Global Situation § Increased Mo-99 Production Capacity – Mo-99 suppliers – acquire additional capacity to cover shortfalls (Outage
    [Show full text]
  • Depleted Uranium Technical Brief
    Disclaimer - For assistance accessing this document or additional information,please contact [email protected]. Depleted Uranium Technical Brief United States Office of Air and Radiation EPA-402-R-06-011 Environmental Protection Agency Washington, DC 20460 December 2006 Depleted Uranium Technical Brief EPA 402-R-06-011 December 2006 Project Officer Brian Littleton U.S. Environmental Protection Agency Office of Radiation and Indoor Air Radiation Protection Division ii iii FOREWARD The Depleted Uranium Technical Brief is designed to convey available information and knowledge about depleted uranium to EPA Remedial Project Managers, On-Scene Coordinators, contractors, and other Agency managers involved with the remediation of sites contaminated with this material. It addresses relative questions regarding the chemical and radiological health concerns involved with depleted uranium in the environment. This technical brief was developed to address the common misconception that depleted uranium represents only a radiological health hazard. It provides accepted data and references to additional sources for both the radiological and chemical characteristics, health risk as well as references for both the monitoring and measurement and applicable treatment techniques for depleted uranium. Please Note: This document has been changed from the original publication dated December 2006. This version corrects references in Appendix 1 that improperly identified the content of Appendix 3 and Appendix 4. The document also clarifies the content of Appendix 4. iv Acknowledgments This technical bulletin is based, in part, on an engineering bulletin that was prepared by the U.S. Environmental Protection Agency, Office of Radiation and Indoor Air (ORIA), with the assistance of Trinity Engineering Associates, Inc.
    [Show full text]
  • Spent Fuel Reprocessing
    Spent Fuel Reprocessing Robert Jubin Oak Ridge National Laboratory Reprocessing of used nuclear fuel is undertaken for several reasons. These include (1) recovery of the valuable fissile constituents (primarily 235U and plutonium) for subsequent reuse in recycle fuel; (2) reduction in the volume of high-level waste (HLW) that must be placed in a geologic repository; and (3) recovery of special isotopes. There are two broad approaches to reprocessing: aqueous and electrochemical. This portion of the course will only address the aqueous methods. Aqueous reprocessing involves the application of mechanical and chemical processing steps to separate, recover, purify, and convert the constituents in the used fuel for subsequent use or disposal. Other major support systems include chemical recycle and waste handling (solid, HLW, low-level liquid waste (LLLW), and gaseous waste). The primary steps are shown in Figure 1. Figure 1. Aqueous Reprocessing Block Diagram. Head-End Processes Mechanical Preparations The head end of a reprocessing plant is mechanically intensive. Fuel assemblies weighing ~0.5 MT must be moved from a storage facility, may undergo some degree of disassembly, and then be sheared or chopped and/or de-clad. The typical head-end process is shown in Figure 2. In the case of light water reactor (LWR) fuel assemblies, the end sections are removed and disposed of as waste. The fuel bundle containing the individual fuel pins can be further disassembled or sheared whole into segments that are suitable for subsequent processing. During shearing, some fraction of the radioactive gases and non- radioactive decay product gases will be released into the off-gas systems, which are designed to recover these and other emissions to meet regulatory release limits.
    [Show full text]
  • Uranium 2001: Resources, Production and Demand
    A Joint Report by the OECD Nuclear Energy Agency and the International Atomic Energy Agency Uranium 2001: Resources, Production and Demand NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT Pursuant to Article 1 of the Convention signed in Paris on 14th December 1960, and which came into force on 30th September 1961, the Organisation for Economic Co-operation and Development (OECD) shall promote policies designed: − to achieve the highest sustainable economic growth and employment and a rising standard of living in Member countries, while maintaining financial stability, and thus to contribute to the development of the world economy; − to contribute to sound economic expansion in Member as well as non-member countries in the process of economic development; and − to contribute to the expansion of world trade on a multilateral, non-discriminatory basis in accordance with international obligations. The original Member countries of the OECD are Austria, Belgium, Canada, Denmark, France, Germany, Greece, Iceland, Ireland, Italy, Luxembourg, the Netherlands, Norway, Portugal, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The following countries became Members subsequently through accession at the dates indicated hereafter: Japan (28th April 1964), Finland (28th January 1969), Australia (7th June 1971), New Zealand (29th May 1973), Mexico (18th May 1994), the Czech Republic (21st December 1995), Hungary (7th May 1996), Poland (22nd November 1996), Korea (12th December 1996) and the Slovak Republic (14 December 2000). The Commission of the European Communities takes part in the work of the OECD (Article 13 of the OECD Convention).
    [Show full text]
  • Security Operational Skills 2 (Tracing).P65
    Unit - 4 K Operating Skill for handling Natural Disasters Structure 4.1 Objectives 4.2 Introduction 4.3 Operating Skill for natural and nuclear disasters 4.4 Accident Categories 4.5 Nuclear and radiation accidents and incidents 4.6 Geological disasters 4.7 Operating Skills for handling Mines and other Explosive Devices 4.8 Operating Skills for handing hijacking situation (other than an airline hijacking 4.9 Operating skills for antivehicle theft operations 4.10 Operating skills for facing a kidnapping or hostage situation 4.11 Operating Skill for handling coal mines and other explosive devices 4.12 Hostage Rights : Law and Practice in Throes of Evolution 4.12.1 Terminology 4.13 Relative Value of Rights 4.14 Conflict of Rights and Obligations 4.15 Hong Kong mourns victims of bus hijacking in the Philoppines 4.16 Rules for Successful Threat Intelligence Teams 4.16.1 Tailor Your Talent 4.16.2 Architect Your Infrastructure 4.16.3 Enable Business Profitability 4.16.4 Communicate Continuously 4.17 Construction Safety Practices 4.17.1 Excavation 4.17.2 Drilling and Blasting 4.17.3 Piling and deep foundations 234 4.18 Planning 4.18.1 Steps in Planning Function 4.18.2 Characteristics of planning 4.18.3 Advantages of planning 4.18.4 Disadvantages of planning 4.1 Objectives The following is a list of general objectives departments should consider when creating an Information Disaster Prevention and Recovery Plan: O Ensure the safety of all employees and visitors at the site/facility O Protect vital information and records O Secure business sites
    [Show full text]
  • GAO-15-141, SPENT NUCLEAR FUEL MANAGEMENT: Outreach
    United States Government Accountability Office Report to Congressional Requesters October 2014 SPENT NUCLEAR FUEL MANAGEMENT Outreach Needed to Help Gain Public Acceptance for Federal Activities That Address Liability GAO-15-141 D October 2014 SPENT NUCLEAR FUEL MANAGEMENT Outreach Needed to Help Gain Public Acceptance for Federal Activities That Address Liability Highlights of GAO-15-141, a report to congressional requesters Why GAO Did This Study What GAO Found DOE is responsible for disposing of Spent nuclear fuel—the used fuel removed from nuclear power reactors—is commercial spent nuclear fuel. DOE expected to accumulate at an average rate of about 2,200 metric tons per year in entered into contracts with owners and the United States. This spent nuclear fuel is mostly stored wet, submerged in generators of spent nuclear fuel to pools of water. However, since pools have been reaching their capacities, begin disposing of it beginning in 1998, owners and generators of spent nuclear fuel (typically utilities and reactor with plans for disposal in a national operators) have been transferring it to canisters that are placed in casks on repository. DOE, however, was unable concrete pads for dry storage—which is an expensive and time-consuming to meet the 1998 date and, as a result process. When operating reactors’ licenses begin to expire in the 2030s, the rate of lawsuits, the federal government has of spent nuclear fuel accumulation is expected to decrease, but the amount in dry paid out about $3.7 billion for storage storage will increase as the pools are closed and all spent nuclear fuel is costs.
    [Show full text]
  • The Supply of Medical Isotopes
    The Supply of Medical Isotopes AN ECONOMIC DIAGNOSIS AND POSSIBLE SOLUTIONS The Supply of Medical Isotopes AN ECONOMIC DIAGNOSIS AND POSSIBLE SOLUTIONS The Supply of Medical Isotopes AN ECONOMIC DIAGNOSIS AND POSSIBLE SOLUTIONS This work is published under the responsibility of the Secretary-General of the OECD. The opinions expressed and arguments employed herein do not necessarily reflect the official views of OECD member countries. This document, as well as any data and any map included herein, are without prejudice to the status of or sovereignty over any territory, to the delimitation of international frontiers and boundaries and to the name of any territory, city or area. Please cite this publication as: OECD/NEA (2019), The Supply of Medical Isotopes: An Economic Diagnosis and Possible Solutions, OECD Publishing, Paris, https://doi.org/10.1787/9b326195-en. ISBN 978-92-64-94550-0 (print) ISBN 978-92-64-62509-9 (pdf) The statistical data for Israel are supplied by and under the responsibility of the relevant Israeli authorities. The use of such data by the OECD is without prejudice to the status of the Golan Heights, East Jerusalem and Israeli settlements in the West Bank under the terms of international law. Photo credits: Cover © Yok_onepiece/Shutterstock.com. Corrigenda to OECD publications may be found on line at: www.oecd.org/about/publishing/corrigenda.htm. © OECD 2019 You can copy, download or print OECD content for your own use, and you can include excerpts from OECD publications, databases and multimedia products in your own documents, presentations, blogs, websites and teaching materials, provided that suitable acknowledgement of OECD as source and copyright owner is given.
    [Show full text]
  • Advanced Reactors with Innovative Fuels
    Nuclear Science Advanced Reactors with Innovative Fuels Workshop Proceedings Villigen, Switzerland 21-23 October 1998 NUCLEAR•ENERGY•AGENCY OECD, 1999. Software: 1987-1996, Acrobat is a trademark of ADOBE. All rights reserved. OECD grants you the right to use one copy of this Program for your personal use only. Unauthorised reproduction, lending, hiring, transmission or distribution of any data or software is prohibited. You must treat the Program and associated materials and any elements thereof like any other copyrighted material. All requests should be made to: Head of Publications Service, OECD Publications Service, 2, rue AndrÂe-Pascal, 75775 Paris Cedex 16, France. OECD PROCEEDINGS Proceedings of the Workshop on Advanced Reactors with Innovative Fuels hosted by Villigen, Switzerland 21-23 October 1998 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT Pursuant to Article 1 of the Convention signed in Paris on 14th December 1960, and which came into force on 30th September 1961, the Organisation for Economic Co-operation and Development (OECD) shall promote policies designed: − to achieve the highest sustainable economic growth and employment and a rising standard of living in Member countries, while maintaining financial stability, and thus to contribute to the development of the world economy; − to contribute to sound economic expansion in Member as well as non-member countries in the process of economic development; and − to contribute to the expansion of world trade on a multilateral, non-discriminatory basis in accordance with international obligations. The original Member countries of the OECD are Austria, Belgium, Canada, Denmark, France, Germany, Greece, Iceland, Ireland, Italy, Luxembourg, the Netherlands, Norway, Portugal, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States.
    [Show full text]