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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 -
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. -
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. -
小型飛翔体/海外 [Format 2] Technical Catalog Category
小型飛翔体/海外 [Format 2] Technical Catalog Category Airborne contamination sensor Title Depth Evaluation of Entrained Products (DEEP) Proposed by Create Technologies Ltd & Costain Group PLC 1.DEEP is a sensor analysis software for analysing contamination. DEEP can distinguish between surface contamination and internal / absorbed contamination. The software measures contamination depth by analysing distortions in the gamma spectrum. The method can be applied to data gathered using any spectrometer. Because DEEP provides a means of discriminating surface contamination from other radiation sources, DEEP can be used to provide an estimate of surface contamination without physical sampling. DEEP is a real-time method which enables the user to generate a large number of rapid contamination assessments- this data is complementary to physical samples, providing a sound basis for extrapolation from point samples. It also helps identify anomalies enabling targeted sampling startegies. DEEP is compatible with small airborne spectrometer/ processor combinations, such as that proposed by the ARM-U project – please refer to the ARM-U proposal for more details of the air vehicle. Figure 1: DEEP system core components are small, light, low power and can be integrated via USB, serial or Ethernet interfaces. 小型飛翔体/海外 Figure 2: DEEP prototype software 2.Past experience (plants in Japan, overseas plant, applications in other industries, etc) Create technologies is a specialist R&D firm with a focus on imaging and sensing in the nuclear industry. Createc has developed and delivered several novel nuclear technologies, including the N-Visage gamma camera system. Costainis a leading UK construction and civil engineering firm with almost 150 years of history. -
Radiation Hazard Location
Radiation Hazard Location Radiation Detector JS Stanley US Patent 8,399.859 B2 March 19, 2013 Using semi spherical PRESAGE with a lead collimator to detect contaminated Hot Cells Improving the Presage Polymer Radiosensitivity for Hot Cell and Glovebox 3D Characterization Adamovics, John; Farfan, Eduardo B.; Coleman, J. Rusty Health Physics (2013), 104(1), 63-67. RadBall is a novel, passive, radiation detection device that provides 3D mapping of radiation from areas where measurements have not been possible previously due to lack of access or extremely high radiation doses. This kind of technol. is beneficial when decommissioning and decontamination of nuclear facilities occur. The key components of the RadBall technol. include a tungsten outer shell that houses a radiosensitive PRESAGE polymer. The 1.0-cm-thick tungsten shell has a no. of holes that allow photons to reach the polymer, thus generating radiation tracks that are analyzed. Submerged RadBall Deployments in Hanford Site Hot Cells Containing 137CsCl Capsules Farfan, Eduardo B.; Coleman, J. Rusty; Stanley, Steven; Adamovics, John; Oldham, Mark; Thomas, Andrew Health Physics 103:100-106 (2012) The overall objective of this study was to demonstrate that a new technol., known as RadBall, could locate submerged radiol. hazards. RadBall is a novel, passive, radiation detection device that provides a 3-D visualization of radiation from areas where measurements have not been previously possible due to lack of access or extremely high radiation doses. This technol. has been under development during recent years, and all of its previous tests have included dry deployments. This study involved, for the first time, underwater RadBall deployments in hot cells contg. -
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. -
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. -
An Introduction to Nuclear Power – Science, Technology and UK
sustainable development commission The role of nuclear power in a low carbon economy Paper 1: An introduction to nuclear power – science, technology and UK policy context An evidence-based report by the Sustainable Development Commission March 2006 Table of contents 1 INTRODUCTION ................................................................................................................................. 3 2 ELECTRICITY GENERATION ................................................................................................................. 4 2.1 Nuclear electricity generation ................................................................................................. 4 2.2 Fission – how does it work?..................................................................................................... 4 2.3 Moderator ................................................................................................................................. 5 2.4 Coolant...................................................................................................................................... 5 2.5 Radioactivity ............................................................................................................................. 6 3 THE FUEL CYCLE: FRONT END ............................................................................................................ 7 3.1 Mining and milling ................................................................................................................... 7 3.2 Conversion and -
Learning from Fukushima: Nuclear Power in East Asia
LEARNING FROM FUKUSHIMA NUCLEAR POWER IN EAST ASIA LEARNING FROM FUKUSHIMA NUCLEAR POWER IN EAST ASIA EDITED BY PETER VAN NESS AND MEL GURTOV WITH CONTRIBUTIONS FROM ANDREW BLAKERS, MELY CABALLERO-ANTHONY, GLORIA KUANG-JUNG HSU, AMY KING, DOUG KOPLOW, ANDERS P. MØLLER, TIMOTHY A. MOUSSEAU, M. V. RAMANA, LAUREN RICHARDSON, KALMAN A. ROBERTSON, TILMAN A. RUFF, CHRISTINA STUART, TATSUJIRO SUZUKI, AND JULIUS CESAR I. TRAJANO Published by ANU Press The Australian National University Acton ACT 2601, Australia Email: [email protected] This title is also available online at press.anu.edu.au National Library of Australia Cataloguing-in-Publication entry Title: Learning from Fukushima : nuclear power in East Asia / Peter Van Ness, Mel Gurtov, editors. ISBN: 9781760461393 (paperback) 9781760461409 (ebook) Subjects: Nuclear power plants--East Asia. Nuclear power plants--Risk assessment--East Asia. Nuclear power plants--Health aspects--East Asia. Nuclear power plants--East Asia--Evaluation. Other Creators/Contributors: Van Ness, Peter, editor. Gurtov, Melvin, editor. All rights reserved. No part of this publication may be reproduced, stored in a retrieval system or transmitted in any form or by any means, electronic, mechanical, photocopying or otherwise, without the prior permission of the publisher. Cover design and layout by ANU Press. Cover image: ‘Fukushima apple tree’ by Kristian Laemmle-Ruff. Near Fukushima City, 60 km from the Fukushima Daiichi Nuclear Power Plant, February 2014. The number in the artwork is the radioactivity level measured in the orchard—2.166 microsieverts per hour, around 20 times normal background radiation. This edition © 2017 ANU Press Contents Figures . vii Tables . ix Acronyms and abbreviations . -
Characteristics of Spent Nuclear Fuel and Cladding Relevant to High-Level Waste Source Term-CNWRA 93-006 Property of CNWRA 93-006 CNWRA Library
CNWRA 93-006 :~~~~~~~~~ I I S _~~~~~~~~~~~ Prepared for Nuclear Regulatory Commission Contract NRC-02-88-005 Prepared by Center for Nuclear Waste Regulatory Analyses San Antonio, Texas May 1993 462.2 --- T19930511000 8 Characteristics of Spent Nuclear Fuel and Cladding Relevant to High-Level Waste Source Term-CNWRA 93-006 Property of CNWRA 93-006 CNWRA Library CHARACTERISTICS OF SPENT NUCLEAR FUEL AND CLADDING RELEVANT TO HIGH-LEVEL WASTE SOURCE TERM Prepared for Nuclear Regulatory Commission Contract NRC-02-88-005 Prepared by Hersh K. Manaktala Center for Nuclear Waste Regulatory Analyses San Antonio, Texas May 1993 PREVIOUS REPORTS IN SERIES Number Name Date Issued CNWRA 92-017 An Assessment of Borosilicate Glass as a High-Level Waste Form September 1992 CNWRA 92-018 Leaching of Borosilicate Glass Using Draft ASTM Procedure for High-Level Waste August 1992 ii --- ABSTRACT This report, based on literature study, describes characteristics of light water reactor (LWR) fuel assemblies for boiling water reactors (BWR) and pressurized water reactors (PWR) and the changes that take place in both cladding and uranium dioxide fuel during service in commercial power reactors. This information is provided as a background for the evaluation of important factors related to fuel stability under geologic repository conditions. Data related to discharged fuel storage (both wet and dry) are also provided, along with the condition of the fuel in terms of damaged and leaking fuel assemblies. The degradation of spent fuel and cladding while in service in the reactor and likely degradation in a geologic repository are discussed in terms of cladding oxidation and corrosion, and fuel-pellet cracking, fuel restructuring, microstructure and fission product mobility, inventory and distribution of fission products, fuel pellet rim effect, and fission gas release and pressure increase. -
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. -
Kwantitatieve Bepaling Van De Invloed Van Experimenteel Gevonden
Kwantitatieve bepaling van de invloed van experimenteel gevonden microstructurele veranderingen, geïnduceerd door neutronenstraling, op de hardheid van modellegeringen en staalsoorten Experimental Quantification of the Effect of Neutron Irradiation Induced Microstructural Changes on the Hardening of Model Alloys and Steels Marlies Lambrecht Promotoren: Prof. Dr. Ir. Y. Houbaert en Dr. A. Almazouzi Proefschrift ingediend tot het behalen van de graad van Doctor in de Ingenieurswetenschappen: Materiaalkunde Voorzitter: Prof. Dr. Ir. J. Degrieck Faculteit Ingenieurswetenschappen Academiejaar 2008-2009 ISBN 978-90-8578-294-0 NUR 971 Wettelijk depot: D/2009/10.500/52 Dit onderzoek werd uitgevoerd aan het onderzoekscentrum This research was performed at the research centre Structural Materials (NMA) group Laboratory for medium and high activity (LHMA) Nuclear Materials Science (NMS) Institute SCK•CEN Boeretang 200 2400 Mol Onder begeleiding van Under guidance of Dr. Abderrahim Almazouzi Dr. Lorenzo Malerba In samenwerking met In collaboration with Vakgroep Toegepaste Materiaalwetenschappen Faculteit Toegepaste Wetenschappen Universiteit Gent (UGent) Technologiepark 903 9053 Zwijnaarde Met promotor With promoter Prof. Dr. Ir. Yvan Houbaert Deels gefinancierd door Partially financed by FI60-CT-2003-5088-40 FP6_PERFECT project The European commision Foreword Foreword I really enjoyed realizing this PhD thesis! The results presented in this thesis are the outcome of a fruitful collaboration between the University of Ghent and the research centre SCK•CEN and I was the chosen one to accomplish the work. I hereby had the possibility to combine pleasure with work. The proposal laid within the scope of my interest, as I could approach engineering problems (the hardening and embrittlement of the RPV steels) using fundamental physics (the defects visualized by the positron technique in model alloys).