The Nuclear Illustrative Programme of the Commission (PINC), and Is a Collection of Factual Data Gathered from Several Sources
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Small Isn't Always Beautiful Safety, Security, and Cost Concerns About Small Modular Reactors
Small Isn't Always Beautiful Safety, Security, and Cost Concerns about Small Modular Reactors Small Isn't Always Beautiful Safety, Security, and Cost Concerns about Small Modular Reactors Edwin Lyman September 2013 © 2013 Union of Concerned Scientists All rights reserved Edwin Lyman is a senior scientist in the Union of Concerned Scientists Global Security Program. The Union of Concerned Scientists puts rigorous, independent science to work to solve our planet’s most pressing problems. Joining with citizens across the country, we combine technical analysis and effective advocacy to create innovative, practical solutions for a healthy, safe, and sustainable future. More information is available about UCS at www.ucsusa.org. This report is available online (in PDF format) at www.ucsusa.org/SMR and may also be obtained from: UCS Publications 2 Brattle Square Cambridge, MA 02138-3780 Or, email [email protected] or call (617) 547-5552. Design: Catalano Design Front cover illustrations: © LLNL for the USDOE (background); reactors from top to bottom: © NuScale Power, LLC, © Holtec SMR, LLC, © 2012 Babcock & Wilcox Nuclear Energy, Inc., and © Westinghouse Electric Company. Back cover illustrations: © LLNL for the USDOE (background); © Westinghouse Electric Company (reactor). Acknowledgments This report was made possible by funding from Park Foundation, Inc., Wallace Research Foundation, an anonymous foundation, and UCS members. The author would like to thank Trudy E. Bell for outstanding editing, Rob Catalano for design and layout, Bryan Wadsworth for overseeing production, and Scott Kemp, Lisbeth Gronlund, and David Wright for useful discussions and comments on the report. The opinions expressed herein do not necessarily reflect those of the organizations that funded the work or the individuals who reviewed it. -
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. -
Analysis on the Thermal Striping and Thermal Shock of the Lower Head of Central Measuring Shroud in a Fast Reactor
Transactions, SMiRT-25 Charlotte, NC, USA, August 4-9, 2019 Division III Analysis on the Thermal Striping and Thermal Shock of the Lower Head of Central Measuring Shroud in a Fast Reactor Zheng Shu 1, Lu Daogang 1, Cao Qiong 1 1School of Nuclear Science and Engineering, Beijing Key Laboratory of Passive Nuclear Safety Technology for Nuclear Energy, North China Electric Power University, Beijing 102206, China ([email protected]) ABSTRACT The central measuring shroud, as an important in-vessel component, contains the conduits of control rod and a variety of measuring equipment. The distance between the core outlet and the lower head of central measuring shroud (LHCMS), which is located above the core outlet, is only 500mm. Therefore, the LHCMS is affected by the core coolant for a long period, especially the temperature effects of the following two types. Firstly, under the operating condition of the sodium-cooled fast reactor, the uneven distribution of the core power causes the phenomenon of thermal striping, which may cause large stress. In addition, under the scram condition, the coolant temperature at the core outlet is sharply reduced due to the decrease of the core power, inducing the phenomenon of thermal shock that may induce large stress. Therefore, stress analysis of the LHCMS under the operating condition and scram condition is very necessary. In the paper, the simulation first established the finite element model of the LHCMS, and then calculated the thermal stress of the LHCMS according to the temperature fluctuation curve and the scram temperature curve. The results show that the temperature field under thermal shock changes dramatically with time, while the temperature field under thermal striping changes relatively slowly with time. -
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 -
From Gen I to Gen III
From Gen I to Gen III Gabriel Farkas Slovak University of Technology in Bratislava Ilkovicova 3, 81219 Bratislava [email protected] 14. 9. 2010 1 Evolution of Nuclear Reactors Generation I - demonstration reactors Generation II - working in the present Generation III - under construction 14. 9. 2010 2 Generation IV - R&D 14. 9. 2010 3 Expected development in nuclear technologies Prolongation of lifetieme of existing nuclear reactors Construction of new reactors in frame of Gen. III and IV . Figure 1 Replacement staggered over a 30-year period (2020 - 2050) Rate of construction : 2,000 MW/year 70000 60000 Lifetime 50000 prolongation 40000 Generation IV 30000 Actual reactors 20000 Generation III+ 10000 0 197519801985199019952000200520102015202020252030203520402045205020552060 14. 9. 2010 Average plant life : 48 years 4 Nuclear in Europe (Nuclear ~ 32% of total EU electricity production) SE, 7.3% UK, 7.9% SP, 5.8% BE,4.8% CZ, 2.5% GE, 16.3% FI, 2.4% BU, 1.8% Other 12.4% SK, 1.7% HU, 1.4% LT, 1.1% FR, 45.5% SI, 0.6% NL, RO, 0.5% 0.4% Source PRIS 14. 9. 2010 5 Central & Eastern Europe - Nuclear Landscape Russia Lithuania Ukraine 6 VVER440 Poland 1 RBMK 1300 2 VVER440 8 VVER1000 Min. of Energy 13 VVER1000 NNEGC State owned 11 RBMK 1 BN600 4 Graph Mod BWR Czech Republic Rosenergoatom State 4 VVER440 owned 2 VVER1000 CEZ/ 67% State Romania owned 2 Candu PHW Nuclearelectrica State owned Slovak Republic 4/6 VVER440 Bulgaria ENEL 67% owned 2/4 VVER1000 NEC State owned Hungary Armenia 4 VVER 440 1 VVER440 MVM State owned Armatomenergo, State owned 14. -
Vver and Rbmk Cross Section Libraries for Origen-Arp
VVER AND RBMK CROSS SECTION LIBRARIES FOR ORIGEN-ARP Germina Ilas, Brian D. Murphy, and Ian C. Gauld, Oak Ridge National Laboratory, USA Introduction An accurate treatment of neutron transport and depletion in modern fuel assemblies characterized by heterogeneous, complex designs, such as the VVER or RBMK assembly configurations, requires the use of advanced computational tools capable of simulating multi-dimensional geometries. The depletion module TRITON [1], which is part of the SCALE code system [2] that was developed and is maintained at the Oak Ridge National Laboratory (ORNL), allows the depletion simulation of two- or three-dimensional assembly configurations and the generation of burnup-dependent cross section libraries. These libraries can be saved for subsequent use with the ORIGEN-ARP module in SCALE. This later module is a faster alternative to TRITON for fuel depletion, decay, and source term analyses at an accuracy level comparable to that of a direct TRITON simulation. This paper summarizes the methodology used to generate cross section libraries for VVER and RBMK assembly configurations that can be employed in ORIGEN-ARP depletion and decay simulations. It briefly describes the computational tools and provides details of the steps involved. Results of validation studies for some of the libraries, which were performed using isotopic assay measurement data for spent fuel, are provided and discussed. Cross section libraries for ORIGEN-ARP Methodology The TRITON capability to perform depletion simulations for two-dimensional (2-D) configurations was implemented by coupling of the 2-D transport code NEWT with the point depletion and decay code ORIGEN-S. NEWT solves the transport equation on a 2-D arbitrary geometry grid by using an SN approach, with a treatment of the spatial variable that is based on an extended step characteristic method [3]. -
Les Réacteurs Expérimentaux Et Leur Contrôle ▼ Les Réacteurs Expérimentaux Et Leur Contrôle Experimental Reactors and Their Regulation
Dossier: Les réacteurs expérimentaux et leur contrôle ▼ Les réacteurs expérimentaux et leur contrôle Experimental reactors and their regulation Chargement de la cuve du réacteur à haut flux (RHF). 2 Dossier: Les réacteurs expérimentaux et leur contrôle ▼ Éditorial 4 Foreword Le contrôle des réacteurs expérimentaux : la démarche de l’Autorité de sûreté nucléaire 5 Experimental reactor regulation: the Nuclear Safety Authority’s approach LE RÔLE DES RÉACTEURS EXPÉRIMENTAUX Le poids des réacteurs expérimentaux dans les programmes de recherche : l’exemple de l’énergie nucléaire 15 The importance of experimental reactors for research programs: The example of nuclear energy Les réacteurs expérimentaux 20 The experimental nuclear reactors La contribution des réacteurs d’expérimentation aux recherches sur la sûreté 27 Contribution of research reactors to the programmes for research and technological development on the safety LES SPÉCIFICITÉS DU CONTRÔLE DES RÉACTEURS EXPÉRIMENTAUX La spécificité du contrôle des réacteurs expérimentaux: le point de vue de l’inspecteur de l’ASN 35 The specific nature of experimental reactor regulation: the viewpoint of ASN’s inspectors La sûreté des réacteurs de recherche vue du Groupe permanent réacteurs 41 Research reactor safety from the advisory committee for nuclear reactors standpoint Les facteurs organisationnels et humains et la sûreté des réacteurs d’expérimentation 47 The human factors and the safety of experimentation reactors Les réexamens de sûreté des réacteurs d’expérimentation en France 52 Periodic safety review management for french research reactors CONCILIER RECHERCHE ET SÛRETÉ: LES RÉPONSES DES EXPLOITANTS ET DES CONCEPTEURS Un enjeu majeur: concilier recherche et sûreté. Le point de vue du CEA 58 A major issue: reconciling research and safety. -
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. -
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. -
India: Protests Against Koodankulam Nuclear
FEBRUARY 8, 2007 | No. 652 INDIA: PROTESTS AGAINST KOODANKULAM NUCLEAR PROJECT INDIA: PROTESTS AGAINST KOODANKULAM NUCLEAR Our most decent, most democratic and most lameduck Prime PROJECT 1 Minister Manmohan Singh signed a deal for four additional USA: NRC MUST REVIEW nuclear plants at Koodankulam with the Russian President Putin N-TERRORISM IN CALIFORNIA on January 27, 2007 even before the public hearing process was LICENSING 2 held for the same. The first hearing was held on October 6. Some SWEDEN: LEAKED REPORT 700 to 800 people unexpectedly turned up and the group REVEALS SAFETY BREACHES AT included many rural women who were not reluctant to speak FORSMARK 3 their minds. The meeting prematurely ended in chaos. The SWEDEN: NUCLEAR CHALLENGE second hearing was scheduled for January 31. TO ENVIRONMENTAL CODE (652.5782) SACCER - Alarmed by the Koodankulam authorities cunningly FAILS 4 plan of the Koodankulam authorities to ducked and conveniently claimed that NUCLEAR POWER POLICY IN take water from the Pechiparai irrigation they were setting up desalination plants EUROPE 5 dam in Kanyakumari district, several with Israeli technology and hence they farmers' organizations and fisherpeople's were not going to take Pechiparai dam ENERGY (R)EVOLUTION: A associations started organizing against water. When we pointed out their claim SUSTAINABLE WORLD ENERGY that dangerous move. This dam water in the official EIA report and in a recent OUTLOOK 6 plan was recorded in the official EIA journal article written by a senior nuclear IN BRIEF 8 (Environmental Impact Assessment) official, they claimed that they were all report that the Koodankulam authorities mistakes. -
Nuscale Energy Supply for Oil Recovery and Refining Applications
Proceedings of ICAPP 2014 Charlotte, USA, April 6-9, 2014 Paper 14337 NuScale Energy Supply for Oil Recovery and Refining Applications D. T. Ingersoll,a C. Colbert,a R. Bromm,b and Z. Houghtona aNuScale Power, LLC 1100 NE Circle Blvd, Suite 200, Corvallis, OR 97330 bFluor Corporation 100 Fluor Daniel Dr., Greenville, SC 29607 Tel: 541-360-0585 , Email: [email protected] Abstract – The oil recovery and refining market is highly energy intensive, representing roughly 7% of the total U.S. energy consumption. The NuScale small modular reactor design is especially well suited for supplying clean, reliable energy to this market due to the compact size of the reactor and the high degree of modularity included in the design, allowing multiple reactors to be combined into a scalable central plant. A preliminary technical and economic assessment has been completed to evaluate the feasibility and desirability of using NuScale power modules to support oil recovery and refining processes, thus reducing the overall carbon footprint of these industrial complexes and preserving valuable fossil resources as feedstock for higher value products. I. INTRODUCTION modular reactors (SMR), are generally characterized by having unit power outputs of less than 300 MWe and are The production of refined petroleum products is highly substantially manufactured in a factory and installed at the energy intensive with most of the energy being used either site rather than constructed on-site. in the field for crude oil recovery processes or at a refinery A new SMR design that has been under development for processing of the crude oil into end-use products such in the United States since 2000 is the NuScale design that as transportation fuels or petrochemicals.