Nuclear Reactor Hazards
Total Page:16
File Type:pdf, Size:1020Kb
Load more
Recommended publications
-
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. -
Deployability of Small Modular Nuclear Reactors for Alberta Applications Report Prepared for Alberta Innovates
PNNL-25978 Deployability of Small Modular Nuclear Reactors for Alberta Applications Report Prepared for Alberta Innovates November 2016 SM Short B Olateju (AI) SD Unwin S Singh (AI) A Meisen (AI) DISCLAIMER NOTICE This report was prepared under contract with the U.S. Department of Energy (DOE), as an account of work sponsored by Alberta Innovates (“AI”). Neither AI, Pacific Northwest National Laboratory (PNNL), DOE, the U.S. Government, nor any person acting on their behalf makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by AI, PNNL, DOE, or the U.S. Government. The views and opinions of authors expressed herein do not necessarily state or reflect those of AI, PNNL, DOE or the U.S. Government. Deployability of Small Modular Nuclear Reactors for Alberta Applications SM Short B Olateju (AI) SD Unwin S Singh (AI) A Meisen (AI) November 2016 Prepared for Alberta Innovates (AI) Pacific Northwest National Laboratory Richland, Washington 99352 Executive Summary At present, the steam requirements of Alberta’s heavy oil industry and the Province’s electricity requirements are predominantly met by natural gas and coal, respectively. On November 22, 2015 the Government of Alberta announced its Climate Change Leadership Plan to 1) phase out all pollution created by burning coal and transition to more renewable energy and natural gas generation by 2030 and 2) limit greenhouse gas (GHG) emissions from oil sands operations. -
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 . -
1194 the Evolution and Future Development of the High
GENES4/ANP2003, Sep. 15-19, 2003, Kyoto, JAPAN Paper 1194 The Evolution and Future Development of the High Temperature Gas Cooled Reactor H. L. Brey* Consultant to the Japan Atomic Energy Research Institute This report chronologically traces the development of the high temperature gas cooled reactor (HTGR) and includes an examination of current international research activities and plant designs. The evolution of the HTGR as a safe, environmentally agreeable and efficient energy source for the generation of electricity and for a broad range of high temperature industrial heat applications has been on-going throughout the past four decades. This report depicts the development of the HTGR through international plant designs and selected facilities from initial research to the present focus on the modular gas turbine and high temperature heat applications such as the production of hydrogen 1,2). This advanced nuclear heat process, with an average core outlet temperature approaching 950°C and using ceramic coated fuel in a helium cooled, graphite matrix, provides a broad and unique set of features and physical properties for scientific investigation as a major energy source for supporting the needs of society well into the 21st century. This paper provides a review of current HTGR related R & D activities including an overview of the HTTR and HTR-10 test reactors, status of GT-MHR and PBMR plant development, the U.S. HTGR programme and a synopsis of the multi-national efforts of the EC and Generation IV nuclear power technology program. KEYWORDS: advanced reactor designs and development; gas cooled reactors I. Introduction Interest in the HTGR has resulted in a wide array of international research and development activities including the multi-national efforts of the EC, Generation The historical development of the HTGR is traced IV nuclear power technology and on-going R&D within through individual plant designs and selected facilities the Member States associated with the IAEA. -
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). -
Reactor Types[Edit]
methods of control of rate of fusion reaction The only known way to control a fusion reaction is with an extremely strong and shaped/focused magnetic field. With today's technology we cannot yet make it strong enough. It breaks up in milliseconds after the reaction, stopping the reaction. types of nuclear materials Nuclear material refers to the metals uranium, plutonium, and thorium, in any form, according to the IAEA. This is differentiated further into "source material", consisting of natural and depleted uranium, and "special fissionable material", consisting of enriched uranium (U- 235), uranium-233, and plutonium-239. fissile and fertile materials Fertile material Fertile material is a material that, although not itself fissionable by thermal neutrons, can be converted into a fissile material by neutron absorption and subsequent nuclei conversions In nuclear engineering, fertile material (nuclide) is material that can be converted to fissile material by neutron. Nuclear reactors elements A nuclear reactor, formerly known as an atomic pile, is a device used to initiate and control a self- sustained nuclear chain reaction. Nuclear reactors are used at nuclear power plants for electricity generation and in nuclear marine propulsion. Heat from nuclear fission is passed to a working fluid (water or gas), which in turn runs through steam turbines. These either drive a ship's propellers or turn electrical generators' shafts. Nuclear generated steam in principle can be used for industrial process heat or for district heating. Some reactors are used to produce isotopes for medical and industrial use, or for production of weapons-grade plutonium. As of early 2019, the IAEA reports there are 454 nuclear power reactors and 226 nuclear research reactors in operation around the world. -
Travis-Carless-Phd-Thesis-2018.Pdf
Framing a New Nuclear Renaissance Through Environmental Competitiveness, Community Characteristics, and Cost Mitigation Through Passive Safety Submitted in partial fulfillment of the requirements for the degree of Doctor of Philosophy in Engineering and Public Policy Travis Seargeoh Emile Carless B.S., Computer and Systems Engineering, Rensselaer Polytechnic Institute M.S., Industrial Engineering, University of Pittsburgh Carnegie Mellon University Pittsburgh, PA May 2018 © Travis Seargeoh Emile Carless, 2018 All Rights Reserved For Angella Clarke, the strongest person I will ever know iv Acknowledgements First and foremost I would like to give all glory to God. I am truely blessed to be given the opportunity to pursue my dream. I would like to dedicate this work to my older cousin Angella Clarke and my friend Javon Jackson whose lives ended far too soon. Within my extended family, Angella was the first person to attend college and nurtured my intellectual curiosity for as long as I can remember. In 1996, I fondly remember attending her graduation from Cornell University. When she was on stage to receive her diploma, I turned to my mother and said to her, “Don’t worry mom, one day you will see me down there.” She was the person in my life that encouraged me to study engineering after recognizing my aptitude in the math and sciences. Quite simply, I would not be the person I am today without her in my life. When I was younger I would race behind you. I would stumble, I would fall. But as I got older, over time, your example has helped me accomplished wonders. -
Nuclear Power in East Asia
4 A new normal? The changing future of nuclear energy in China M . V . Ramana and Amy King Abstract In recent years, China has reduced its goal for expanding nuclear power capacity, from a target of 70 gigawatts (GW) by 2020 issued in 2009 to just 58 GW by 2020 issued in 2016 . This chapter argues that this decline in targets stems from three key factors. The first factor is China’s transition to a relatively low-growth economy, which has led to correspondingly lower levels of growth in demand for energy and electricity . Given China’s new low- growth economic environment, we argue that the need for rapid increases in nuclear power targets will likely become a thing of the past . The second factor is the set of policy changes adopted by the Chinese government following the March 2011 Fukushima Daiichi nuclear disaster in Japan . Since the Fukushima disaster, China’s State Council has stopped plans for constructing inland nuclear reactors and restricted reactor construction to modern (third-generation) designs . The third factor is government responsiveness to public opposition to the siting of nuclear facilities near population centres . Collectively, these factors are likely to lead to a decline in the growth rate of nuclear power in China . 103 LEARNING FROM FUKUSHIMA Introduction In March 2016, China’s National People’s Congress endorsed its draft 13th Five Year Plan (2016–20), which set China the goal of developing 58 gigawatts (GW) of operating nuclear capacity by 2020, with another 30 GW to be under construction by then. At first glance, this goal appears ambitious, for it represents a doubling of China’s current nuclear capacity of 29 GW (as of May 2016, according to the International Atomic Energy Agency’s (IAEA) Power Reactor Information System (PRIS) database). -
Signature Research on Legacy Management at the National Nuclear Laboratory, United Kingdom - 10362
Signature Research on Legacy Management at the National Nuclear Laboratory, United Kingdom - 10362 A. W. Banford National Nuclear Laboratory, Risley, Warrington, Cheshire, WA3 6AS, United Kingdom ABSTRACT The United Kingdom (UK) National Nuclear Laboratory (NNL) is establishing four Signature Research Areas, which will underpin the future requirements of the UK nuclear Industry. The management of radioactive waste, nuclear plant and sites at the end of operations is a significant challenge in the UK and internationally. Therefore the NNL Signature Research Area on Legacy Management aims to address this challenge. The key theme of the research area is to inform and underpin the development of strategies for legacy management through an understanding of the nature of the waste inventory, the potential endpoints and the identification of possible processing options. This strategic approach aims to identify the key challenges, identify required evolutionary changes to existing technologies and identify areas in which revolutionary change could make most impact. This paper provides a technical overview of the UK’s National Nuclear Laboratory Signature Research Area on Legacy Management; which will focus on the range of technical areas notably; • strategy development • waste, facility and land characterisation • waste behaviour • decontamination • retrieval and remote deployment • decommissioning techniques • contaminated land and site end points. INTRODUCTION A series of four Signature Research Areas have been identified as being central to the United Kingdom National Nuclear Laboratory mission, to provide independent, authoritative advice on nuclear issues. These areas encompass activities which are of strategic significance to the NNL and both the UK and international nuclear industry. The four areas are defined as follows, • Fuel and Reactors • Spent Fuel and Nuclear Materials [1] • Legacy Waste and Decommissioning • Waste Processing, Storage and Disposal Collectively these areas cover most of the nuclear fuel cycle. -
The Utilization of Thorium in Advanced Pwr- from Small to Big Reactors
THE UTILIZATION OF THORIUM IN ADVANCED PWR- FROM SMALL TO BIG REACTORS J. R. Maiorino1,2 1Federal University of ABC- Brazil 2University of Pisa-Italy IV SENCIR Semana de Engenharia Nuclear e Ciências das Radiações CONTENT • Introduction - Uranium -Thorium • Utilization of thorium in PWR reactors • Advanced PWR: Small and Big -Big Advanced PWR -Advanced Small Modular Reactors • Conversion of Advanced PWR for thorium utilization - Big Advanced PWR- The feasibility to convert AP 1000 for using (U/Th)O2 -Small Modular Reactors- The feasibility to convert SMART for using (U/Th)O2 • Utilization in others Advanced and Innovative Reactors and Fuel Cycles NPP in operation worldwide • Mainly pressurized water reactors (PWR) are used in the nuclear power plants world-wide – 65 % according to the number, 70 % according to the output - followed by boiling water reactors (BWR) – 17 % according to the number, 19 % according to the output. • Most of these Reactors are Generation II reactors constructed in the XX century and uses UO2 as fuel and operates in a OTC cycle. The average age of these reactors are ~30 years. Utilization of Natural Resource= 0.005 Burn Up~30 MWd/kgU Uranium Production and Demand Generation III Advanced Reactors • Design Standardization to expedite licensing (pre-licensing), diminishing construction time implying in reducing the capital cost (economics criteria); • Simplified Design to simplify the operation and reduce the operational faults; • Greater availability, increase the time between refuelling, and increase the plant life time (60 year); • Minimization of the possibility of Core Meltdown; Utilization of Natural Resource= • Emergency coolant system, passive; 0.01 • Greater Burn up (60 MWD/ Kg U) and reduces the waste production; • Utilization of advanced fixed burn up poison to increase the fuel lifetime. -
O.E.C. D. High Temperature Reactor Project
O.E.C. D. RA HIGH TEMPERATURE REACTOR PROJECT TV ORGANISATION FOR ECONOMIC COOPERATION AND DEVELOPMENT NUCLEAR ENERGY AGENCY O.E.C.D. HIGH TEMPERATURE REACTOR PROJECT ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT NUCLEAR ENERGY AGENCY The Organisation for Economic Co-operation and Devel• opment (OEGD) was set up under a Convention signed in Paris on 14th December, 1960, which provides that the OECD shall pro• mote 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; •— to contribute to the expansion of world trade on a multi• lateral, non-discriminatory basis in accordance with inter• national obligations. The Members of OECD are Australia, Austria, Belgium, Cana• da, Denmark, Finland, .France, the Federal Republic of Germany, Greece, Iceland, Ireland, Italy, Japan, Luxembourg, the Nether• lands, N'ew Zealand, Norway, Portugal, Spain, Sweden, Switzer• land, Turkey, the United Kingdom and the United States. The OECD Nuclear Energy Agency (NEA) was established on L'olh April i[)/L>. replacing OECD's European Nuclear Energy Agency (ENEA) on the adhesion of Japan as a full Member. NEA now groups all the European Member countries of OECD and Australia, Canada, Japan, and the United States. The Commission of the European Communities takes part in the work of the Agency. The objectives of NEA remain substantially those of ENEA , namely the orderly development of the uses of nuclear energy for peaceful pui poses.