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1, 2002, Sheraton Crystal City Hotel, Arlington, Virginia
Minutes for the Nuclear Energy Research Advisory Committee Meeting September 30 to October 1, 2002, Sheraton Crystal City Hotel, Arlington, Virginia NERAC members present: John Ahearne Dale Klein (Monday only) Thomas Cochran Robert Long Joseph Comfort Warren F. Miller, Jr. Michael Corradini Sekazi Mtingwa Jose Luis Cortez Richard Reba (Monday only) Maureen Crandall (Monday afternoon Joy Rempe and Tuesday only) Allen Sessoms Allen Croff Daniel Sullivan James Duderstadt (Chair) John Taylor Marvin Fertel (Monday only) Neil Todreas Beverly Hartline Joan Woodard (Monday only) Andrew Klein NERAC members absent: Steve Fetter Lura Powell Leslie Hartz C. Bruce Tarter J. Bennett Johnston Ashok Thadani (ad hoc) Linda C. Knight Charles E. Till Benjamin F. Montoya Also present: Ralph Bennett, Director for Advanced Nuclear Energy, Idaho National Engineering and Environmental Laboratory David Berg, Office of Environmental Management, DOE Nancy Carder, NERAC Staff Herbert Feinroth, President, Gamma Engineering Corp. John Gutteridge, University Programs, NE, USDOE Norton Haberman, Senior Technical Advisor, NE, USDOE Anthony Hechanova, Director, AAA University Participation Program, University of Nevada at Las Vegas R. Shane Johnson, Associate Director, Office of Technology and International Cooperation, NE, USDOE Silvia Jurisson, Department of Chemistry, University of Missouri, Columbia Owen Lowe, Associate Director, Office of Isotopes for Medicine and Science, NE, USDOE William Magwood, Director, NE, USDOE William Martin, Washington Policy Institute -
Ceramic Mineral Waste-Forms for Nuclear Waste Immobilization
materials Review Ceramic Mineral Waste-Forms for Nuclear Waste Immobilization Albina I. Orlova 1 and Michael I. Ojovan 2,3,* 1 Lobachevsky State University of Nizhny Novgorod, 23 Gagarina av., 603950 Nizhny Novgorod, Russian Federation 2 Department of Radiochemistry, Lomonosov Moscow State University, Moscow 119991, Russia 3 Imperial College London, South Kensington Campus, Exhibition Road, London SW7 2AZ, UK * Correspondence: [email protected] Received: 31 May 2019; Accepted: 12 August 2019; Published: 19 August 2019 Abstract: Crystalline ceramics are intensively investigated as effective materials in various nuclear energy applications, such as inert matrix and accident tolerant fuels and nuclear waste immobilization. This paper presents an analysis of the current status of work in this field of material sciences. We have considered inorganic materials characterized by different structures, including simple oxides with fluorite structure, complex oxides (pyrochlore, murataite, zirconolite, perovskite, hollandite, garnet, crichtonite, freudenbergite, and P-pollucite), simple silicates (zircon/thorite/coffinite, titanite (sphen), britholite), framework silicates (zeolite, pollucite, nepheline /leucite, sodalite, cancrinite, micas structures), phosphates (monazite, xenotime, apatite, kosnarite (NZP), langbeinite, thorium phosphate diphosphate, struvite, meta-ankoleite), and aluminates with a magnetoplumbite structure. These materials can contain in their composition various cations in different combinations and ratios: Li–Cs, Tl, Ag, Be–Ba, Pb, Mn, Co, Ni, Cu, Cd, B, Al, Fe, Ga, Sc, Cr, V, Sb, Nb, Ta, La, Ce, rare-earth elements (REEs), Si, Ti, Zr, Hf, Sn, Bi, Nb, Th, U, Np, Pu, Am and Cm. They can be prepared in the form of powders, including nano-powders, as well as in form of monolith (bulk) ceramics. -
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. -
IMT Atlantique, Orano, Naval Group Et L'irsn Reconduisent La Chaire
Le 15/05/2018 Communiqué de presse IMT Atlantique, Orano, Naval Group et l’IRSN reconduisent la chaire RESOH avec l’Andra pour nouveau partenaire Lancée en 2012, par IMT Atlantique et ses trois partenaires Orano, Naval Group et l’IRSN, la chaire de recherche et d’enseignement RESOH « REcherche en Sûreté Organisation Hommes » constitue une démarche innovante. Elle réunit des exploitants du nucléaire et l’institut d’expertise d’appui de l’Autorité de sûreté autour d’une volonté commune de réfléchir et d’agir au service d’une performance industrielle « sûre ». La convention signée au début de l’année 2018 reconduit la chaire RESOH jusqu’en octobre 2022 et marque l’arrivée d’un nouveau partenaire, l’Andra (Agence nationale pour la gestion des déchets radioactifs). La chaire RESOH-2 s’appuiera sur les acquis et l’originalité de RESOH-1, qui a permis d’initier des collaborations inédites en matière de recherche et des discussions entre les acteurs de la sûreté nucléaire. Ce projet met l’accent sur les relations inter-organisationnelles et marque la volonté de ne pas isoler la sûreté nucléaire des autres formes de performance industrielle, faisant ainsi émerger le concept de « performance industrielle sûre ». RESOH-2 reprend et approfondit les 3 axes de recherche initialement définis, avec la volonté de renforcer les liens transversaux entre ces différents domaines : • Gestion des projets complexes, • Pilotage de la valeur des relations de sous-traitance (engagements contractuels, travailler ensemble). • Relations contrôleur-contrôlé et gestion de l’équilibre entre sécurité réglée et sécurité gérée. Cette seconde étape est aussi l’occasion de capitaliser sur la connaissance des sites des partenaires industriels et de valider l’investissement de terrain effectué pour appréhender la complexité d’équipements tels que La Hague, le chantier de construction des sous-marins nucléaires d’attaque de classe Barracuda, ou des activités d’expertise de l’IRSN (Institut de Radioprotection et de Sûreté Nucléaire). -
Recueil Des Actes Administratifs De La Manche
PREFET DE LA MANCHE RECUEIL DES ACTES ADMINISTRATIFS DE LA MANCHE DOCUMENTATION ET INFORMATIONS JANVIER 2020 Le contenu intégral des textes et/ou les documents et plans annexés peut être consulté auprès du service sous le timbre duquel la publication est réalisée et sur le site Internet de la préfecture : http://www.manche.gouv.fr Rubrique : Publications - Annonces et avis - Recueil des actes administratifs 2 SOMMAIRE CABINET DU PREFET ..................................................................................................................................................................................... 3 Arrêté n° 19-588 du 20 décembre 2019 portant attribution de la médaille d’honneur du Travail - Promotion du 01 janvier 2020 .................... 3 Arrêté n° 20-001 du 6 janvier 2020 modifiant l’arrêté préfectoral accordant la médaille d’honneur Agricole, promotion du 1er janvier 2020 ..................................................................................................................................................................................................... 14 Arrêté n° 20-002 du 6 janvier 2020 modifiant l’arrêté préfectoral portant attribution de la médaille d’honneur Régionale, Départementale et Communale, promotion du 1er janvier 2020 ...................................................................................................................... 14 SOUS-PREFECTURE DE CHERBOURG ...................................................................................................................................................... -
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. -
WHAT WILL ADVANCED NUCLEAR POWER PLANTS COST? a Standardized Cost Analysis of Advanced Nuclear Technologies in Commercial Development
WHAT WILL ADVANCED NUCLEAR POWER PLANTS COST? A Standardized Cost Analysis of Advanced Nuclear Technologies in Commercial Development AN ENERGY INNOVATION REFORM PROJECT REPORT PREPARED BY THE ENERGY OPTIONS NETWORK TABLE OF CONTENTS Executive Summary 1 1. Study Motivation and Objectives 6 Why Care about Advanced Nuclear Costs? 7 Origins of This Study 8 A Standardized Framework for Cost Analysis 8 2. Results 9 3. Study Methodology 14 EON Model 15 Company Preparedness and Strategies 19 Limits of This Analysis 20 Certainty Levels for Advanced Nuclear Cost Estimates 20 Realistic Considerations That May Influence Cost 21 4. Advanced Nuclear’s Design and Delivery Innovations 22 Context: The Cost of Conventional Nuclear 23 Design Considerations for Conventional Nuclear Reactors 24 Safety Enhancements of Advanced Nuclear 24 Overview of Reactor Designs 25 Delivery Issues with Conventional Nuclear Power 27 Innovations in the Delivery of Advanced Nuclear Technologies 28 Design Factors That Could Increase Advanced Nuclear Costs 30 5. Conclusions 31 6. References 32 Appendix A: Nuclear Plant Cost Categories 34 Appendix B: Operating Costs for a Nuclear Plant 35 Appendix C: Cost Category Details and Modeling Methodology 36 Appendix D: External Expert Review of Draft Report 43 THE FUTURE OF NUCLEAR TECHNOLOGY: A STANDARDIZED COST ANALYSIS EXECUTIVE SUMMARY Advanced nuclear technologies are controversial. Many people believe they could be a panacea for the world’s energy problems, while others claim that they are still decades away from reality and much more complicated and costly than conventional nuclear technologies. Resolving this debate requires an accurate and current understanding of the increasing movement of technology development out of national nuclear laboratories and into private industry. -
Progress in Nuclear Energy 105 (2018) 83–98
Progress in Nuclear Energy 105 (2018) 83–98 Contents lists available at ScienceDirect Progress in Nuclear Energy journal homepage: www.elsevier.com/locate/pnucene Technology perspectives from 1950 to 2100 and policy implications for the T global nuclear power industry Victor Nian Energy Studies Institute, National University of Singapore, Singapore ARTICLE INFO ABSTRACT Keywords: There have been two completed phases of developments in nuclear reactor technologies. The first phase is the Nuclear industry trends demonstration of exploratory Generation I reactors. The second phase is the rapid scale-up of Generation II Nuclear energy policy reactors in North America and Western Europe followed by East Asia. We are in the third phase, which is the ff Technology di usion construction of evolutionary Generation III/III+ reactors. Driven by the need for safer and more affordable New user state nuclear reactors post-Fukushima, the nuclear industry has, in parallel, entered the fourth phase, which is the International cooperation development of innovative Generation IV reactors. Through a comprehensive review of the historical reactor Advanced reactor development technology developments in major nuclear states, namely, USA, Russia, France, Japan, South Korea, and China, this study presents a projection on the future potentials of advanced reactor technologies, with particular focus on pressurized water reactors, high temperature reactors, and fast reactors, by 2100. The projected potentials provide alternative scenarios to develop insights that complement the established technology roadmaps. Findings suggest that there is no clear winner among these technologies, but fast reactors could demonstrate a new and important decision factor for emerging markets. Findings also suggest small modular reactors, espe- cially those belonging to Generation IV, as a transitional technology for developing domestic market and in- digenous technology competence for emerging nuclear states. -
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. -
Fast-Spectrum Reactors Technology Assessment
Clean Power Quadrennial Technology Review 2015 Chapter 4: Advancing Clean Electric Power Technologies Technology Assessments Advanced Plant Technologies Biopower Clean Power Carbon Dioxide Capture and Storage Value- Added Options Carbon Dioxide Capture for Natural Gas and Industrial Applications Carbon Dioxide Capture Technologies Carbon Dioxide Storage Technologies Crosscutting Technologies in Carbon Dioxide Capture and Storage Fast-spectrum Reactors Geothermal Power High Temperature Reactors Hybrid Nuclear-Renewable Energy Systems Hydropower Light Water Reactors Marine and Hydrokinetic Power Nuclear Fuel Cycles Solar Power Stationary Fuel Cells U.S. DEPARTMENT OF Supercritical Carbon Dioxide Brayton Cycle ENERGY Wind Power Clean Power Quadrennial Technology Review 2015 Fast-spectrum Reactors Chapter 4: Technology Assessments Background and Current Status From the initial conception of nuclear energy, it was recognized that full realization of the energy content of uranium would require the development of fast reactors with associated nuclear fuel cycles.1 Thus, fast reactor technology was a key focus in early nuclear programs in the United States and abroad, with the first usable nuclear electricity generated by a fast reactor—Experimental Breeder Reactor I (EBR-I)—in 1951. Test and/or demonstration reactors were built and operated in the United States, France, Japan, United Kingdom, Russia, India, Germany, and China—totaling about 20 reactors with 400 operating years to date. These previous reactors and current projects are summarized in Table 4.H.1.2 Currently operating test reactors include BOR-60 (Russia), Fast Breeder Test Reactor (FBTR) (India), and China Experimental Fast Reactor (CEFR) (China). The Russian BN-600 demonstration reactor has been operating as a power reactor since 1980. -
APR1400 Chapter 12, "Radiation Protection," Final Safety Evaluation Report
12 RADIATION PROTECTION Chapter 12, “Radiation Protection,” of this safety evaluation report (SER) describes the results of the review by the staff of the U.S. Nuclear Regulatory Commission (NRC), hereinafter referred to as the staff, of the Design Control Document (DCD), for the design certification (DC) of the Advanced Power Reactor 1400 (APR1400), submitted by Korea Electric Power Corporation (KEPCO) and Korea Hydro & Nuclear Power Co., Ltd (KHNP), hereinafter referred to as the applicant. This chapter also provides information on facility and equipment design and programs used to meet the radiation protection standards of Title 10 of the Code of Federal Regulations (10 CFR), Part 20, “Standards for Protection Against Radiation,” Part 50, “Domestic Licensing of Production and Utilization Facilities,” and Part 70, “Domestic Licensing of Special Nuclear Material.” The staff evaluated the information in Chapter 12, “Radiation Protection,” of the APR1400 DCD against the guidance in NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition” (hereafter referred to as the SRP), Chapter 12, “Radiation Protection.” Compliance with these criteria provides assurance that doses to workers will be maintained within the occupational dose limits of 10 CFR Part 20, “Standards for Protection Against Radiation.” These occupational dose limits, applicable to workers at NRC- licensed facilities, restrict the sum of the external whole-body dose (deep-dose equivalent) and the committed effective equivalent doses resulting from radioactive material deposited inside the body (deposited through injection, absorption, ingestion, or inhalation) to 50 millisievert (mSv) (5 roentgen equivalent man [rem]) per year with a provision (i.e., by planned special exposure) to extend this dose to 100 mSv (10 rem) per year with a lifetime dose limit of 250 mSv (25 rem) resulting from planned special exposures. -
Is There a Niche for Concentrated Solar Power?
energies Article A Comparison of Dispatchable RES Technoeconomics: Is There a Niche for Concentrated Solar Power? Alexandra G. Papadopoulou 1,2,* , George Vasileiou 1,2 and Alexandros Flamos 1 1 Department of Industrial Management and Technology, Technoeconomics of Energy Systems Laboratory (TEESlab), University of Piraeus (UNIPI), Karaoli & Dimitriou 80, 18534 Piraeus, Greece; [email protected] (G.V.); afl[email protected] (A.F.) 2 School of Electrical and Computer Engineering, Decision Support Systems Laboratory (DSSLab), National Technical University of Athens, Iroon Politechniou 9, 15773 Athens, Greece * Correspondence: [email protected] Received: 16 July 2020; Accepted: 8 September 2020; Published: 12 September 2020 Abstract: Raising the penetration of renewable energy sources constitutes one of the main pillars of contemporary decarbonization strategies. Within this context, further progress is required towards the optimal exploitation of their potential, especially in terms of dispatchability, where the role of storage is considered vital. Although current literature delves into either storage per se or the integration of storage solutions in single renewable technologies, the comparative advantages of each technology remain underexplored. However, high-penetration solutions of renewable energy sources (RES) are expected to combine different technological options. Therefore, the conditions under which each technology outperforms their counterparts need to be thoroughly investigated, especially in cases where storage components are included. This paper aims to deal with this gap, by means of assessing the combination of three competing technologies, namely concentrated solar power (CSP), photovoltaics (PV) and offshore wind, with the storage component. The techno-economic assessment is based on two metrics; the levelized cost of electricity and the net present value.