Data Documentation
Total Page:16
File Type:pdf, Size:1020Kb
Load more
Recommended publications
-
Selection of Retrieval Techniques for Irradiated Graphite During Reactor Decommissioning - 11587
WM2011 Conference, February 27 - March 3, 2011, Phoenix, AZ Selection of Retrieval Techniques for Irradiated Graphite during Reactor Decommissioning - 11587 D.J. Potter*, R.B. Jarvis*, A.W. Banford*, L. Cordingley*, and M. Grave** * National Nuclear Laboratory, Chadwick House, Birchwood Park, Warrington, Cheshire, WA3 6AE, UK ** Doosan Babcock, Baltic Business Centre, Gateshead, NE8 3DA, UK ABSTRACT Globally, around 230,000 tonnes of irradiated graphite requires retrieval, treatment, management and/or disposal. This waste has arisen from a wide range of reactors, predominantly from the use of graphite moderated reactors for base-load generation, but also from experimental research facilities. Much of the graphite is presently still in the reactor core while other graphite is stored in a variety of forms in waste stores. The first step in the management of this significant waste stream is retrieval of the graphite from its present location. Doosan Babcock and the UK National Nuclear Laboratory are participants in the CARBOWASTE European research project which brings together organisations from a range of countries with an irradiated graphite legacy to address the graphite waste management challenge. This paper describes the issues associated with retrieval of graphite from reactors, potential approaches to graphite retrieval and the information needed to select a particular retrieval method for a specified application. Graphite retrieval is viewed within the context of the wider strategy for the management of irradiated graphite waste streams. The paper identifies the challenges of graphite retrieval and provides some examples where modelling can be used to provide information to support retrievals design and operations. INTRODUCTION A four year collaborative European Project ‘Treatment and Disposal of Irradiated Graphite and other Carbonaceous Waste (CARBOWASTE)’ was launched in April 2008 under the 7th EURATOM Framework Programme [1]. -
Developing an Intergovernmental Nuclear Regulatory Organization
Developing an Intergovernmental Nuclear Regulatory Organization: Lessons Learned from the International Civil Aviation Organization, the International Maritime Organization, and the International Telecommunication Union Clarence Eugene Carpenter, Jr. Bachelor of Science in Mechanical Engineering, May 1988 Seattle University, Seattle, WA Master of Science in Technical Management, May 1997 The Johns Hopkins University, Baltimore, MD Master of Arts in International Science and Technology Policy, May 2009 The George Washington University, Washington, DC A Dissertation submitted to The Faculty of The Columbian College of Arts and Sciences of The George Washington University in partial fulfillment of the requirements for the degree of Doctor of Philosophy January 10, 2020 Dissertation directed by Kathryn Newcomer Professor of Public Policy and Public Administration The Columbian College of Arts and Sciences of The George Washington University certifies that Clarence Eugene Carpenter, Jr. has passed the Final Examination for the degree of Doctor of Philosophy as of November 26, 2019. This is the final and approved form of the dissertation. Developing an Intergovernmental Nuclear Regulatory Organization: Lessons Learned from the International Civil Aviation Organization, the International Maritime Organization, and the International Telecommunication Union Clarence Eugene Carpenter, Jr. Dissertation Research Committee: Kathryn Newcomer, Professor of Public Policy and Public Administration, Dissertation Director Philippe Bardet, Assistant Professor, -
Accident and Safety Analysis of the Ks-150 Reactor
ZJl-120 1972 J.HMWM ACCIDENT AND SAFETY ANALYSIS OF THE KS-150 REACTOR SKODA WORKS Niriiir Powtr CoMtrvdiofl DtpartMtnt, Information Contra . PLŽEM - CZECHOSLOVAKIA We regret that some of the pages in the microfiche copy of this report may not be up to the proper legibility standards, even though the best possible copy was used for preparing the master fiche. £ 1ÍQ "far. liniové.:- : С I D E II T л i: D ti A P В T Y ANALYSIS OF TUK К G - i. 5 O REACTOR O!. ,л.и V/ORKS .fiai' Power CŮHÍJÍ/Í .ir.txori Гера^аито, Information Centre Notation 3 1. Introduction: 4 Й» Tfe* state-of-art and the development trends in the safety of power reactors 8 2 л feclear reactor as a source of potential danger 9 2.2 A brief review of nuclear reactor safety 11 •'o? Development of safety philosophy 14 Z Л Зй?е<^у devices of nuclear reactors 18 3e Thff A~l nuclear power statioa 24 ЗЛ The main data sheet 24 3.2 Power statiac maia equipment and its thermal schematic chart 26 3e3 The control system 39 3 4 The system of safety 43 4. The method of the XS~150 reactor safety analysis 50 4»! Comparison of the KS=>150 reactor with other gas cooled reactors» Requirements laid on realtor safety 50 4-B2 The method of analysis 54 4.3 Extreme initiating events 57 i Л Mathematical models 58 5. The KS-15G reactor basic dynamical characteristics 61 5.1 The effect of intrinsic feedbacks 62 5»2 The effect of the control system 63 5 Л Summary 65 6. -
Thermal Hydraulics Analysis of the Distribution Zone in Small Modular Dual Fluid Reactor
metals Article Thermal Hydraulics Analysis of the Distribution Zone in Small Modular Dual Fluid Reactor Chunyu Liu 1,* , Xiaodong Li 1 , Run Luo 1,2 and Rafael Macian-Juan 1 1 Chair of Nuclear Technology, Department of Mechanical Engineering, Technical University of Munich (TUM), Boltzmannstr. 15, 85748 Garching, Germany; [email protected] (X.L.); [email protected] or [email protected] (R.L.); [email protected] (R.M.-J.) 2 School of Resource & Environment and Safety Engineering, University of South China, No. 28, Changsheng West Road, Hengyang 421001, China * Correspondence: [email protected] or [email protected] Received: 29 June 2020; Accepted: 4 August 2020; Published: 6 August 2020 Abstract: The Small Modular Dual Fluid Reactor (SMDFR) is a novel molten salt reactor based on the dual fluid reactor concept, which employs molten salt as fuel and liquid lead/lead-bismuth eutectic (LBE) as coolant. A unique design of this reactor is the distribution zone, which locates under the core and joins the core region with the inlet pipes of molten salt and coolant. Since the distribution zone has a major influence on the heat removal capacity in the core region, the thermal hydraulics characteristics of the distribution zone have to be investigated. This paper focuses on the thermal hydraulics analysis of the distribution zone, which is conducted by the numerical simulation using COMSOL Multiphysics with the CFD (Computational Fluid Dynamics) module and the Heat Transfer module. The energy loss and heat exchange in the distribution zone are also quantitatively analyzed. The velocity and temperature distributions of both molten salt and coolant at the outlet of the distribution zone, as inlet of the core region, are produced. -
Atomová Energie
Atomová Energie (autor : Matyáš Kosík) Obsah : Úvod CO je RADIOAKTIVITA ??? Využití radioaktivity a radioaktivních prvkú Historie jaderného výzkumu a výzkumu radioaktivity Princip jaderných reakcí + Princip Atomových elektráren -Jaderné ŠTEPENÍ a jaderná SYNTÉZA - Typy reaktorú a jejich vlastnosti Výhody jaderných elektráren Na co dávat pozor (na lidi…) - Havárie v černobylu Záver – PROČ se lidé bojí jaderných elektráren (a proč si myslím, že to je nesmysl) Budoucnost (232 Th…) Mýty a odpovedi Shrnutí Zdroje aneb na co a kam se podívat 1.Úvod. Rozhodl jsem se psát tuto práci, protože si myslím, že o jaderné energii koluje dost pověr polopravd a omylů.Např. lidi si myslí, že reaktory jsou nebezpečné, ale to nebezpečné na nich je hlavně možnost lidského selhání. Ta se ovšem může snížit v tom případě, pokud u reaktorů budou pracovat kvalifikovaní a opatrní lidé. Uvést to vše na pravou míru je velice zajímavé téma na seminární práci. V této práci se například dozvíte: kdo první spustil řízenou řetězovou reakci, co se stalo 26. dubna 1986, jaké jsou různé typy reaktorů , jak pracují jaderné reaktory na 235-U, 238-U i 239-Pu či o přeměnách atomu na jiný, což vyvrátilo základ chemie a mnoho dalšího. 2.CO je Radioaktivita ??? Radioaktivita je způsobená tím, že pro některé izotopy různých prvků není jejich (energetický)stav výhodný. Můžou použít různé typy radioaktivního rozpadu, aby v jednom či více krocích dosáhly stability- 3 3 např. Tritium 1H (nejtězší vodík) se v jednom kroku rozpadá beta- rozpadem na helium 2He, 238 které je stabilní. Ale -
Survey of Design and Regulatory Requirements for New Small Reactors, Contract No
Canadian Nuclear Safety Commission - R550.1 Survey of Design and Regulatory Requirements for New Small Reactors, Contract No. 87055-13-0356 Final Report - July 3, 2014 RSP-0299 Canadian Nuclear Safety Commission R550.1 Survey of Design and Regulatory Requirements for New Small Reactors, Contract No. 87055-13-0356 Final Report July 3, Released for Brian Gihm 0 Victor Snell Jim Sarvinis Milan Ducic 2014 Use Victor Snell Date Rev. Status Prepared By Checked By Approved By Approved By Client - CNSC H346105-0000-00-124-0002, Rev. 0 Page i © Hatch 2015 All rights reserved, including all rights relating to the use of this document or its contents. Canadian Nuclear Safety Commission - R550.1 Survey of Design and Regulatory Requirements for New Small Reactors, Contract No. 87055-13-0356 Final Report - July 3, 2014 Executive Summary The objectives of this report are to perform a design survey of small modular reactors (SMRs) with near-term deployment potential, with a particular emphasis on identifying their innovative safety features, and to review the Canadian nuclear regulatory framework to assess whether the current and proposed regulatory documents adequately address SMR licensing challenges. SMRs are being designed to lower the initial financing cost of a nuclear power plant or to supply electricity in small grids (often in remote areas) which cannot accommodate large nuclear power plants (NPPs). The majority of the advanced SMR designs is based on pressurized water reactor (PWR) technology, while some non-PWR Generation IV technologies (e.g., gas-cooled reactor, lead-cooled reactor, sodium-cooled fast reactor, etc.) are also being pursued. -
Jules Horowitz Reactor (JHR), a High-Performance Material Test Reactor in Cadarache, France
The Swedish-French collaboration on the research reactors ASTRID & JHR Prof. Christophe Demazière Chalmers University of Technology Department of Applied Physics Division of Nuclear Engineering [email protected] Background − the ESS project • ESS: European Spallation Source – a European Union facility. • Will be built in Lund. • Participation of France is formalized in a contract between France and Sweden. • Sweden has to spend 400 MSEK on joint research in subjects relevant to France (energy and environment). • Out of this, 100 MSEK is devoted to fission-based nuclear energy. Background – the European research program • Vision: Sustainable Nuclear Energy Technology Platform (SNETP). • Planned facilities: – Jules Horowitz Reactor (JHR), a high-performance material test reactor in Cadarache, France. Start of operation: 2014. – MYRRHA facility in Mol, Belgium, a fast spectrum irradiation facility working as an ADS. Start of operation: ca. 2023. – ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration), a prototype Gen-IV sodium-cooled fast reactor to be built in France. Start of operation: ca. 2020. – VHTR, a first-of-a kind Very High Temperature Reactor for, among others, hydrogen production. VR Multi-project Grant in Nuclear Energy Research • 3 multi-grant projects granted by the Swedish Research Council in the spring of 2012 (projects in collaboration with CEA, France – French Alternative Energies and Atomic Energy Commission): – DEMO-JHR (coordinator: Prof. Christophe Demazière, Chalmers): 3 PhD projects. – ASTRID -
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. -
Presentation Title (On One Or Two Lines)
Energy Business Technology Strategy Yukihiko Kazao Executive Officer and Corporate Senior Vice President Energy Systems & Solutions Company Chief Technology Executive Toshiba Corporation October 18, 2016 © 2016 Toshiba Corporation Energy Business Technology Strategy Pursue clean energy and the related management system グリーンエネルギーの追求とそのマネジメントシステムでand aim to realize sustainable energy for society 持続可能なエネルギー社会の実現を目指す Variable power sources Generate Low carbon Nuclear Hydro- Geothermal Solar Hydrogen thermal power power power power Wind power Transmit Store ・Hydropower ・variable speed Rechargeable batteries Hydrogen water pumps Transformers Short-term Long-term storage storage Transmission Substations Storage and distribution systems Smart use Factories Transport Homes Buildings © 2016 Toshiba Corporation 2 Advancing Toward a Society Supported by Sustainable Energy I. Green energy ・ That pursues the world‘s highest level of safety in nuclear power ・ That aims for zero emissions by introducing high efficiency systems and carbon capture technologies in thermal power ・ That contributes to the stabilization of the power system with hydropower II. Energy management ・ Use next-generation technologies to pursue optimal control of the supply and demand balance Ⅲ. Cutting-edge technologies ・ Lead the world in cutting-edge technologies © 2016 Toshiba Corporation 3 Toshiba Group’s Nuclear Power Plants Global expansion with two reactors offering the world's highest safety levels High capacity BWR: ABWR Innovative PWR: AP1000™ ・ Dynamic + static safety -
Significant Incidents in Nuclear Fuel Cycle Facilities
IAEA-TECDOC-867 Significant incidents in nuclear fuel cycle INTERNATIONAL ATOMIC ENERGY AGENCY The IAEA does not normally maintain stocks of reports in this series. However, microfiche copie f thesso e reportobtainee b n sca d from INIS Clearinghouse International Atomic Energy Agency Wagramerstrasse 5 P.O. Box 100 A-1400 Vienna, Austria Orders should be accompanied by prepayment of Austrian Schillings 100, in the form of a cheque or in the form of IAEA microfiche service coupons which may be ordered separately from the INIS Clearinghouse. The originating Section of this publication in the IAEA was: Nuclear Fuel Cycle and Materials Section International Atomic Energy aoiicy A Wagramerstrasse 5 0 10 P.Ox Bo . A-1400 Vienna, Austria SIGNIFICANT INCIDENT NUCLEASN I R FUEL CYCLE FACILITIES IAEA, VIENNA, 1996 IAEA-TECDOC-867 ISSN 1011-4289 ©IAEA, 1996 Printe IAEe th AustriAn y i d b a March 1996 FOREWORD significano Tw t accidents have occurre histore th n di f nuclea yo r power, namely t Threa , e Mile Islan Chernobyld dan orden I . preveno rt t such accidents, causes were investigate actiond dan s were taken r exampleFo . , reporting systems were establishe accumulato dt disseminatd ean e information on accidents such as INES (International Nuclear Event Scale) and IRS (Incident Reporting System). Operators of nuclear power plants also established an information system to share incident information. The purpose of INES is to facilitate prompt communication between the nuclear community, the media and the public. The purpose of IRS is to analyse causes of significant incidents. Those systems serve to promote safety culture in nuclear power plants. -
A Comparison of Advanced Nuclear Technologies
A COMPARISON OF ADVANCED NUCLEAR TECHNOLOGIES Andrew C. Kadak, Ph.D MARCH 2017 B | CHAPTER NAME ABOUT THE CENTER ON GLOBAL ENERGY POLICY The Center on Global Energy Policy provides independent, balanced, data-driven analysis to help policymakers navigate the complex world of energy. We approach energy as an economic, security, and environmental concern. And we draw on the resources of a world-class institution, faculty with real-world experience, and a location in the world’s finance and media capital. Visit us at energypolicy.columbia.edu facebook.com/ColumbiaUEnergy twitter.com/ColumbiaUEnergy ABOUT THE SCHOOL OF INTERNATIONAL AND PUBLIC AFFAIRS SIPA’s mission is to empower people to serve the global public interest. Our goal is to foster economic growth, sustainable development, social progress, and democratic governance by educating public policy professionals, producing policy-related research, and conveying the results to the world. Based in New York City, with a student body that is 50 percent international and educational partners in cities around the world, SIPA is the most global of public policy schools. For more information, please visit www.sipa.columbia.edu A COMPARISON OF ADVANCED NUCLEAR TECHNOLOGIES Andrew C. Kadak, Ph.D* MARCH 2017 *Andrew C. Kadak is the former president of Yankee Atomic Electric Company and professor of the practice at the Massachusetts Institute of Technology. He continues to consult on nuclear operations, advanced nuclear power plants, and policy and regulatory matters in the United States. He also serves on senior nuclear safety oversight boards in China. He is a graduate of MIT from the Nuclear Science and Engineering Department.