Nuclear Reactors: Generation to Generation
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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 -
Introduction to GE Hitachi
Overview of ABWR Safety Features INPRO Dialogue Forum November 19-23, 2013 J. Alan Beard Principal Engineer Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved GE Hitachi nuclear alliance and businesses Wilmington, NC Tokyo, Japan Wilmington, NC Wilmington, NC Peterborough, ON USA USA Yokosuka, Japan Canada •Nuclear Power Plants: ABWR, •Uranium •Nuclear Fuel Fabrication ESBWR and PRISM Enrichment ….BWR and CANDU •Nuclear Services … Third •CANDU Services •Advanced Programs … Generation •Fuel Engineering and Support Recycling Technology Services •GENUSA European Fuel Joint Venture Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 2 BWR legacy around the world Dodewaard - Netherlands KKM - Switzerland K6/K7 - Japan Dresden 1 – USA KRB - Germany Lungmen - Taiwan Santa María de Garoña - Spain Vallecitos – USA Garigliano - Italy Laguna Verde - Mexico Tarapur 1&2 – India Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 3 Recent project experience Kashiwazaki-Kariwa 6/7 ABWR COD 1996/1997 Hamaoka-5 ABWR COD 2005 Shika-2 ABWR Continuously building for 58 years COD 2006 Images copyright TEPCO, Hokuriku Electric Power, Chugoku Electric Power, and J-Power; Provided by Hitachi GE Nuclear Energy Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved 4 Current project status Ohma ABWR Ohma 1 • 38% complete Shimane 3 • 94% complete Under Construction • Approaching fuel load Shimane-3 ABWR Lungmen 1&2 • 94% complete • Startup and Pre-Op -
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. -
CHAPTER 13 Reactor Safety Design and Safety Analysis Prepared by Dr
1 CHAPTER 13 Reactor Safety Design and Safety Analysis prepared by Dr. Victor G. Snell Summary: The chapter covers safety design and safety analysis of nuclear reactors. Topics include concepts of risk, probability tools and techniques, safety criteria, design basis accidents, risk assessment, safety analysis, safety-system design, general safety policy and principles, and future trends. It makes heavy use of case studies of actual accidents both in the text and in the exercises. Table of Contents 1 Introduction ............................................................................................................................ 6 1.1 Overview ............................................................................................................................. 6 1.2 Learning Outcomes............................................................................................................. 8 1.3 Risk ...................................................................................................................................... 8 1.4 Hazards from a Nuclear Power Plant ................................................................................ 10 1.5 Types of Radiation in a Nuclear Power Plant.................................................................... 12 1.6 Effects of Radiation ........................................................................................................... 12 1.7 Sources of Radiation ........................................................................................................ -
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. -
Light Water Reactor System Designed to Minimize Environmental Burden of Radioactive Waste
Hitachi Review Vol. 63 (2014), No. 9 602 Featured Articles Light Water Reactor System Designed to Minimize Environmental Burden of Radioactive Waste Tetsushi Hino, Dr. Sci. OVERVIEW: One of the problems with nuclear power generation is the Masaya Ohtsuka, Dr. Eng. accumulation in radioactive waste of the long-lived TRUs generated as Kumiaki Moriya byproducts of the fission of uranium fuel. Hitachi is developing a nuclear reactor that can burn TRU fuel and is based on a BWR design that is Masayoshi Matsuura already in use in commercial reactors. Achieving the efficient fission of TRUs requires that the spectrum of neutron energies in the nuclear reactor be modified to promote nuclear reactions by these elements. By taking advantage of one of the features of BWRs, namely that their neutron energy spectrum is more easily controlled than that of other reactor types, the new reactor combines effective use of resources with a reduction in the load on the environment by using TRUs as fuel that can be repeatedly recycled to burn these elements up. This article describes the concept behind the INTRODUCTION RBWR along with the progress of its development, NUCLEAR power generation has an important role to as well as its specifications and features. play in both energy security and reducing emissions of carbon dioxide. One of its problems, however, is the accumulation in radioactive waste from the long- RBWR CONCEPT lived transuranium elements (TRUs) generated as Plutonium Breeding Reactor byproducts of the fission of uranium fuel. The TRUs The original concept on which the RBWR is based include many different isotopes with half-lives ranging was the plutonium generation boiling water reactor from hundreds to tens of thousands of years or more. -
France USA Research
atw Vol. 61 (2016) | Issue 2 ı February safety and was subject to a separate After joint examination of this file global markets, and submitted the set of “conventional” permits. with IRSN, ASN convened the Advi- license application to the NRC in Hanhikivi1 will be a 1,200mega sory Committee for nuclear pressure September. watt VVER pressurised water reactor equipment (GP ESPN) on 30 Septem Westinghouse and Toshiba Corpo 141 of the Russian AES-2006 type. Start of ber 2015. The GP ESPN submitted its ration are working collaboratively on commissioning is scheduled for 2022 opinion and its recommendation to a limited number of customized mate and commercial operation for 2024. ASN. On this basis, ASN issued a rials and/or reinforcements that will | www.fennovoima.fi | 7304 position statement on the procedure allow new units to be built in areas adopted by Areva, with a certain that have a higher seismic condition. NEWS number of observations and add This Specialized Seismic Option will itional requests. provide the same advanced safety France The results of the new test pro features, modular design and simpli gramme will be crucial to ASN’s fied systems as the standard, NRC- Flamanville 3 EPR: ASN has decision on the suitability for service certified AP1000 plant technology. no objection to the initiation of the Flamanville 3 RPV closure head | www.westinghousenuclear.com of a new test programme and bottom head. This test pro | 7283 (asn) On 12 December 2015, ASN gramme will take several months. issued a position statement concern | www.asn.fr | 7290 ing the approach used to demonstrate the mechanical properties of the Research Flamanville 3 EPR reactor pressure vessel (RPV) closure head and bottom USA IPP: The first plasma: head proposed by Areva. -
The Jules Horowitz Reactor Project, a Driver for Revival of the Research Reactor Community
THE JULES HOROWITZ REACTOR PROJECT, A DRIVER FOR REVIVAL OF THE RESEARCH REACTOR COMMUNITY P. PERE, C. CAVAILLER, C. PASCAL AREVA TA CEA Cadarache - Etablissement d'AREVA TA - Chantier RJH - MOE - BV2 - BP n° 9 – 13115 Saint Paul lez Durance - France CS 50497 - 1100, rue JR Gauthier de la Lauzière, 13593 Aix en Provence cedex 3 – France ABSTRACT The first concrete of the nuclear island for the Jules Horowitz Reactor (JHR) was poured at the end of July 2009 and construction is ongoing. The JHR is the largest new platform for irradiation experiments supporting Generation II and III reactors, Generation IV technologies, and radioisotope production. This facility, composed of a unique grouping of workshops, hot cells and hot laboratories together with a first -rate MTR research reactor, will ensure that the process, from preparations for irradiation experiments through post-irradiation non-destructive examination, is completed expediently, efficiently and, of course, safely. In addition to the performance requirements to be met in terms of neutron fluxes on the samples (5x1014 n.cm-2/sec-1 E> 1 MeV in core and 3,6x1014 n.cm-2/sec-1 E<0.625 eV in the reflector) and the JHR’s considerable irradiation capabilities (more than 20 experiments and one-tenth of irradiation area for simultaneous radioisotope production), the JHR is the first MTR to be built since the end of the 1960s, making this an especially challenging project. The presentation will provide an overview of the reactor, hot cells and laboratories and an outline of the key milestones in the project schedule, including initial criticality in early 2014 and radioisotope production in 2015. -
French Nuclear Company Orano Upgraded to 'BB+' on Improved Liquidity and Capital Structure; Outlook Stable
Research Update: French Nuclear Company Orano Upgraded To 'BB+' On Improved Liquidity And Capital Structure; Outlook Stable Primary Credit Analyst: Christophe Boulier, Paris (39) 02-72111-226; [email protected] Secondary Contact: Andrey Nikolaev, CFA, Paris (33) 1-4420-7329; [email protected] Table Of Contents Overview Rating Action Rationale Outlook Ratings Score Snapshot Issue Ratings--Recovery Analysis Related Criteria Ratings List WWW.STANDARDANDPOORS.COM/RATINGSDIRECT APRIL 5, 2018 1 Research Update: French Nuclear Company Orano Upgraded To 'BB+' On Improved Liquidity And Capital Structure; Outlook Stable Overview • Orano has reported EBITDA of close to €1 billion for 2017, despite challenging industry conditions, and its recent restructuring and capital increases have improved its liquidity and capital structure. • We think Orano will continue to focus on cost-cutting and generate moderately positive free operating cash flow, enabling it to reduce net debt in 2018-2020. • Consequently, we are upgrading Orano to 'BB+' from 'BB'. • The stable outlook reflects our view that Orano will be able to reduce adjusted debt to EBITDA to below 5.5x in 2019-2020 despite challenging industry conditions, supported by its sizeable, long-term order backlog. Rating Action On April 5, 2018, S&P Global Ratings raised its long-term issuer credit rating on France-based nuclear services group Orano to 'BB+' from 'BB'. The outlook is stable. We also raised our ratings on Orano's senior unsecured bonds to 'BB+' from 'BB'. Although we expect substantial recovery (70%-90%; rounded estimate 85%) on the bonds in the event of a default, the recovery rating is capped at '3' due to the bonds' unsecured nature and issuance by a company rated in the 'BB' category. -
Press Release
Press release The ATMEA1 reactor pre-qualified in Argentina Paris, July 12, 2012 The national utility Nucleoeléctrica Argentina (NA-SA) has informed ATMEA that it had pre-qualified the ATMEA1 technology for the next Request For Proposals that will be issued for the construction of its fourth nuclear power plant. By pre-selecting the ATMEA1 technology, NA-SA acknowledges that the ATMEA1 reactor is a qualified design that could meet the most stringent safety requirements and fit needs of the NA-SA. “After Jordan pre-selection of the ATMEA1 design last May and as confirmed by the recent positive statement of the French Safety Authority ASN on the ATMEA1 reactor’s safety options, this NA-SA decision confirms the trust being placed in the ATMEA1 technology. I’m confident that its design will fulfil stringent Argentina’s requirements, with its highest safety level as a Generation III+ reactor, its proven technology and its superior operation performance”, outlined Philippe Namy, ATMEA President. In 2006, Argentina announced the reactivation of a strategic plan for the country’s nuclear power sector, including the construction of a fourth nuclear reactor. The ATMEA1 reactor is a pressurized water reactor of 1,100 MWe, intended for any types of electrical networks and in particular for medium power grids. It was designed and developed by ATMEA, the 50/50 Joint Venture created in 2007 by Mitsubishi Heavy Industries and AREVA. Taking support on these two parent companies, ATMEA capitalizes on their experience of about 130 nuclear power plants which are operating in the world for around 50 years, and representing approximately 3300 cumulative reactor years of operation. -
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. -
Research Branch
CA9600028 Background Paper BP-365E THE CANADIAN NUCLEAR POWER INDUSTRY Alan Nixon Science and Technology Division December 1993 Library of Parliament Research Bibliothèque du Parlement Branch The Research Branch of the Library of Parliament works exclusively for Parliament conducting research and providing information for Committees and Members of the Senate and the House of Commons. This service is extended without partisan bias in such forms as Reports, Background Papers and Issue Reviews. Research Officers in the Branch are also available for personal consultation in their respective fields of expertise. ©Minister of Supply and Services Canada 1994 Available in Canada through your local bookseller or by mail from Canada Communication Group -- Publishing Ottawa, Canada K1A 0S9 Catalogue No. YM32-2/365E ISBN 0-660-15639-3 CE DOCUMENT EST AUSSI PUBUÉ EN FRANÇAIS LIBRARY OF PARLIAMENT BIBLIOTHÈQUE OU PARLEMENT TABLE OF CONTENTS Page EARLY CANADIAN NUCLEAR DEVEOPMENT 2 THE CANDU REACTOR 4 NUCLEAR POWER GENERATION IN CANADA 5 A. Background 5 B. Performance 6 C. Pickering Nuclear Generating Station 8 D. Bruce Nuclear Generating Station 9 1. Retubing 9 2. Pressure Tube Frets 10 3. Shut Down System Design Flaw 12 4. Steam Generators 12 E. Darlington 13 1. Start-up Problems 13 2. Costs 14 AECL 15 A. Introduction 15 B. CANDU-Design and Marketing 16 1. Design 16 2. Marketing 17 a. Export Markets 17 b. Domestic Market ! 18 C. AECL Research 19 D. Recent Developments 20 OUTLOOK 21 * CANADA LIBRARY OF PARLIAMENT BIBLIOTHÈQUE DU PARLEMENT THE NUCLEAR POWER INDUSTRY IN CANADA Nuclear power, the production of electricity from uranium through nuclear fission, is by far the most prominent segment of the nuclear industry.