DOCSLIB.ORG

Appendix C October 8, 2014

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Appendix C October 8, 2014 Nuclear Fuel Cycle Evaluation and Screening – Final Report – Appendix C October 8, 2014 APPENDIX C EVALUATION CRITERIA AND METRICS Nuclear Fuel Cycle Evaluation and Screening – Final Report – Appendix C ii October 8, 2014 Nuclear Fuel Cycle Evaluation and Screening – Final Report – Appendix C October 8, 2014 iii CONTENTS C. Evaluation Criteria and Metrics ......................................................................................................... 1 C-1. Nuclear Waste Management Criterion ..................................................................................... 1 C-1.1 Background on Nuclear Waste Management .............................................................. 1 C-1.2 Metric Development for the Nuclear Waste Management Criterion .......................... 5 C-1.3 Mass of SNF+HLW Disposed per Energy Generated ................................................ 6 C-1.4 Activity of SNF+HLW (@100 years) per Energy Generated ..................................... 7 C-1.5 Activity of SNF+HLW (@100,000 years) per Energy Generated .............................. 7 C-1.6 Mass of DU+RU+RTh Disposed per Energy Generated ............................................ 8 C-1.7 Volume of LLW per Energy Generated ...................................................................... 9 References for C-1. ........................................................................................................................... 25 C-2. Proliferation Risk Criterion .................................................................................................... 26 C-2.1 Fuel Cycle Assessments ............................................................................................ 26 C-2.2 Evaluation of Material Attractiveness ....................................................................... 27 References for C-2. ........................................................................................................................... 27 C-3. Nuclear Material Security Risk Criterion .............................................................................. 28 C-3.1 Background on Nuclear Material Security Risk ....................................................... 29 C-3.2 Evaluation of Targets for Malevolent Use ................................................................ 30 References for C-3. ........................................................................................................................... 30 C-4. Safety Criterion ...................................................................................................................... 31 C-4.1 Background on Safety ............................................................................................... 31 C-4.2 Metric Development for the Safety Criterion ........................................................... 33 C-4.3 Challenges of Addressing Safety Hazards ................................................................ 38 C-4.4 Safety of the Deployed System ................................................................................. 40 References for C-4. ........................................................................................................................... 41 C-5. Environmental Impact Criterion ............................................................................................ 41 C-5.1 Background on Environmental Impact ..................................................................... 41 C-5.2 Metric Development for the Environmental Impact Criterion .................................. 41 C-5.3 Land Use per Energy Generated ............................................................................... 46 C-5.4 Water Use per Energy Generated .............................................................................. 54 C-5.5 Carbon Emission - CO2 Released per Energy Generated ......................................... 57 C-5.6 Radiological Exposure - Total Estimated Worker Dose per Energy Generated (as Leading Indicator for Public Dose Potential) ..................................... 64 References for C-5. ........................................................................................................................... 84 C-6. Resource Utilization Criterion ............................................................................................... 89 C-6.1 Background on Resource Utilization ........................................................................ 89 C-6.2 Metric Development for the Resource Utilization Criterion ..................................... 90 C-6.3 Natural Uranium Required per Energy Generated .................................................... 91 C-6.4 Natural Thorium Required per Energy Generated .................................................... 91 C-7. Development and Deployment Risk Criterion ....................................................................... 92 C-7.1 Background on Development and Deployment Risk ................................................ 93 C-7.2 Metric Development for the Development and Deployment Risk Criterion ............ 94 C-7.3 Development Cost ..................................................................................................... 99 C-7.4 Development Time .................................................................................................. 100 C-7.5 Deployment Cost from Prototypic Validation to FOAK Commercial .................... 103 C-7.6 Compatibility with the Existing Infrastructure ....................................................... 105 C-7.7 Existence of Regulations for the Fuel Cycle and Familiarity with Licensing......... 106 Nuclear Fuel Cycle Evaluation and Screening – Final Report – Appendix C iv October 8, 2014 C-7.8 Existence of Market Incentives and/or Barriers to Commercial Implementation of Fuel Cycle Processes ................................................................ 109 References for C-7. ......................................................................................................................... 116 C-8. Institutional Issues Criterion ................................................................................................ 116 C-8.1 Background ............................................................................................................. 117 C-8.2 Metric Development for the Institutional Issues Criterion...................................... 117 C-8.3 Compatibility with Existing Infrastructure ............................................................. 118 C-8.4 Existence of regulations for the fuel cycle and familiarity with licensing .............. 118 C-8.5 Existence of market incentives and/or barriers to commercial implementation of fuel cycle processes .................................................................. 118 C-9. Financial Risk and Economics Criterion .............................................................................. 118 C-9.1 Background on Financial Risk and Economics ...................................................... 119 C-9.2 Metric Development for the Financial Risk and Economics Criterion ................... 119 C-9.3 Levelized Cost of Electricity at Equilibrium .......................................................... 121 References for C-9 .......................................................................................................................... 135 FIGURES Figure C-1.1. Influence Diagram Showing Some of the Factors Affecting the Challenge of Nuclear Waste Management. ................................................................................................ 2 Figure C-3.1. Influence Diagram of the Considerations for the Nuclear Material Security Risk Criterion. ............................................................................................................................. 29 Figure C-4.1. Influence Diagram Illustrating the Primary Factors Related to the Safety Criterion. ........ 32 Figure C-5.1. Influence Diagram for Environmental Impact. ................................................................... 42 Figure C-5.2. Material and Energy Balance for Each NFC Phase. ........................................................... 43 Figure C-5.3. Illustration of Range of Candidate Technologies and Options for Phases of the Nuclear Fuel Cycle. ............................................................................................................ 44 Figure C-5.4. Crystal River Unit 3 Site Boundary and Exclusion Area. [C-5.7]...................................... 49 Figure C-5.5. Land Withdrawal Area. [C-5.11] ........................................................................................ 51 Figure C-6.1. Influence Diagram Showing Some of the Relationships Between Resource Utilization and Other Factors. ............................................................................................ 90 Figure C-7.1. Fuel Cycle Development and Deployment Phases. ............................................................ 93 Figure C-7.2. Development and Deployment Risk Relationships. ........................................................... 94 Figure C-7.3. Influence Diagram for Development and Deployment Risk. ............................................. 94 Figure C-7.4. Technology Readiness Levels. [C-7.1]............................................................................... 95 Figure C-7.5. Influence Diagram for the Existence of Market Incentives. ............................................. 114
Load more

Recommended publications
  • 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,
    [Show full text]
  • The French Approach for the Regulation of Research Reactors
    The French approach for the regulation of research reactors D. Conte, A. Chevallier Autorité de sûreté nucléaire, Paris, France Abstract. The French Nuclear Safety Authority (ASN) regulates civil nuclear facilities in France. In addition to the pool of 58 pressurized water reactors ASN also regulates several research reactors which are all unique installations. The regulatory approach for research reactors takes cognisance of the different level of hazard encountered in their operation and hence requires a different approach to the management of safety in comparison with nuclear power reactor operations. For a number of years, ASN has been striving to optimise its regulation of experimental reactors. To ensure the optimum level of safety by focusing on the most important safety issues and allowing the licensee to exercise its full responsibilities through the use of internal authorisations. The internal authorisations system, which has been in operation for several years now with a number of experimental reactors, is designed to achieve this two-fold objective. In addition to the careful use of a new range of tools for its regulatory framework in the research reactors area, ASN has other safety challenges for example the ageing of most of the existing facilities and the licensing of new reactors with a high international profile such as the Jules Horowitz reactor or the ITER fusion reactor. 1. Introduction The French Nuclear Safety Authority (ASN) regulates civil nuclear facilities in France (164). In addition to the pool of 58 pressurized water reactors ASN also regulates research reactors which are all unique installations. Most of the research reactors are operated by the atomic energy commission (CEA).
    [Show full text]
  • Analysis of Advanced Sodium-Cooled Fast Reactor Core Designs with Improved Safety Characteristics
    Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics THÈSE NO 5480 (2012) PRÉSENTÉE LE 3 SEPTEMBRE 2012 À LA FACULTÉ DES SCIENCES DE BASE LABORATOIRE DE PHYSIQUE DES RÉACTEURS ET DE COMPORTEMENT DES SYSTÈMES PROGRAMME DOCTORAL EN ENERGIE ÉCOLE POLYTECHNIQUE FÉDÉRALE DE LAUSANNE POUR L'OBTENTION DU GRADE DE DOCTEUR ÈS SCIENCES PAR Kaichao SUN acceptée sur proposition du jury: Prof. R. Schaller, président du jury Prof. R. Chawla, directeur de thèse Dr J. Krepel, rapporteur Dr A. Pautz, rapporteur Prof. J. Wallenius, rapporteur Suisse 2012 Abstract In order to meet the steadily increasing worldwide energy demand, nuclear power is expected to continue playing a key role in electricity production. Currently, the large majority of nuclear power plants are operated with thermal-neutron spectra and need regular fuel loading of enriched uranium. According to the identified conventional uranium resources and their current consumption rate, only about 100 years’ nuclear fuel supply is foreseen. A reactor operated with a fast-neutron spectrum, on the other hand, can induce self-sustaining, or even breeding, conditions for its inventory of fissile material, which effectively allow it – after the initial loading – to be refueled using simply natural or depleted uranium. This implies a much more efficient use of uranium resources. Moreover, minor actinides become fissionable in a fast-neutron spectrum, enabling full closure of the fuel cycle and leading to a minimization of long-lived radioactive wastes. The sodium-cooled fast reactor (SFR) is one of the most promising candidates to meet the Generation IV International Forum (GIF) declared goals.
    [Show full text]
  • Oversight of Research Reactors in the Southeast of France: ASN Regulatory Experience
    Oversight of Research Reactors in the Southeast of France: ASN Regulatory Experience Julien Vieuble, Carole Dormant, Pierre Perdiguier Autorité de Sûreté Nucléaire (French Nuclear Safety Authority), Division de Marseille, 67/69 Avenue du Prado, 13 286 Marseille Cedex 6, France Email of the corresponding author: [email protected] The French Nuclear Safety Authority (ASN), which is an independent administrative authority, is in charge of regulating nuclear safety and radiation protection in order to protect workers, patients, the public and the environment from the risks associated with nuclear activities. ASN also contributes to the public information and the promotion of transparency and openness among stakeholders. The key values of ASN are independence, competence, rigor and transparency, enabling its 450 staff to perform their various duties with the needed legitimacy. ASN’s oversight covers more than 160 civil basic nuclear installations all over France. These installations are of very different varieties and sizes: nuclear power plants, research reactors, nuclear laboratories, fuel cycle facilities, and at different stages in their lives: conception, construction, operation, dismantling. ASN also oversees the safety of radioactive material transport. The ASN division of Marseille oversees the nuclear civil activities in the southeast area of France, which covers, inter alia, the nuclear site of Marcoule (4 civil nuclear installations) and the nuclear site of Cadarache (20 civil nuclear installations). The French public Atomic Energy Commission (CEA) has nine research reactors currently in operation: six of them are located in the southeast of France, and a new one, the Jules Horowitz reactor (JHR), is under construction on the nuclear site of Cadarache.
    [Show full text]
  • Plutonium for Energy? Explaining the Glo1bal Decline of MOX
    Stichting Laka: Documentatie- en onderzoekscentrum kernenergie De Laka-bibliotheek The Laka-library Dit is een pdf van één van de publicaties in This is a PDF from one of the publications de bibliotheek van Stichting Laka, het in from the library of the Laka Foundation; the Amsterdam gevestigde documentatie- en Amsterdam-based documentation and onderzoekscentrum kernenergie. research centre on nuclear energy. Laka heeft een bibliotheek met ongeveer The Laka library consists of about 8,000 8000 boeken (waarvan een gedeelte dus ook books (of which a part is available as PDF), als pdf), duizenden kranten- en tijdschriften- thousands of newspaper clippings, hundreds artikelen, honderden tijdschriftentitels, of magazines, posters, video's and other posters, video’s en ander beeldmateriaal. material. Laka digitaliseert (oude) tijdschriften en Laka digitizes books and magazines from the boeken uit de internationale antikernenergie- international movement against nuclear beweging. power. De catalogus van de Laka-bibliotheek staat The catalogue of the Laka-library can be op onze site. De collectie bevat een grote found at our website. The collection also verzameling gedigitaliseerde tijdschriften uit contains a large number of digitized de Nederlandse antikernenergie-beweging en magazines from the Dutch anti-nuclear power een verzameling video's. movement and a video-section. Laka speelt met oa. haar informatie- Laka plays with, amongst others things, its voorziening een belangrijke rol in de information services, an important role in the Nederlandse anti-kernenergiebeweging. Dutch anti-nuclear movement. Appreciate our work? Feel free to make a small donation. Thank you. www.laka.org | [email protected] | Ketelhuisplein 43, 1054 RD Amsterdam | 020-6168294 Plutonium for Energy? Explaining the Glo1bal Decline of MOX A Policy Research Project of the LBJ School ojf Public Affairs University of 'Texas at Austin dNl� NUCLEAR9 PIROLIFERATION�· PREVENT rN PROJECT � th,· llmv•:r'''iof lc••• •• t\u"'" Edited by Alan J.
    [Show full text]
  • System Thermal-Hydraulic Modelling of the Phénix Dissymmetric Test Benchmark V
    System thermal-hydraulic modelling of the phénix dissymmetric test benchmark V. Narcisi, F. Giannetti, A. del Nevo, F. Alcaro, X. Wang, A. Kraus, A. Brunett, J. Thomas, N. Girault, B. Grosjean, et al. To cite this version: V. Narcisi, F. Giannetti, A. del Nevo, F. Alcaro, X. Wang, et al.. System thermal-hydraulic modelling of the phénix dissymmetric test benchmark. Nuclear Engineering and Design, Elsevier, 2019, 353, pp.110272. 10.1016/j.nucengdes.2019.110272. hal-02530000 HAL Id: hal-02530000 https://hal.archives-ouvertes.fr/hal-02530000 Submitted on 2 Apr 2020 HAL is a multi-disciplinary open access L’archive ouverte pluridisciplinaire HAL, est archive for the deposit and dissemination of sci- destinée au dépôt et à la diffusion de documents entific research documents, whether they are pub- scientifiques de niveau recherche, publiés ou non, lished or not. The documents may come from émanant des établissements d’enseignement et de teaching and research institutions in France or recherche français ou étrangers, des laboratoires abroad, or from public or private research centers. publics ou privés. Distributed under a Creative Commons Attribution - NonCommercial - NoDerivatives| 4.0 International License SYSTEM THERMAL-HYDRAULIC MODELLING OF THE PHÉNIX DISSYMMETRIC TEST BENCHMARK V. Narcisi*, F. Giannetti*, A. Del Nevo-, F. Alcaro+, X. Wang°, A. Krausv, A. Brunettv, J. Thomasv, N. Girault⁂, B. Grosjeanx, G. Caruso*, A. Gerschenfeldx * “Sapienza” University of Rome, DIAEE – Nuclear Section, Rome, Italy -Italian National Agency for New Technologies,
    [Show full text]
  • Nuclear Energy of the Future: What Research for Which Objectives?
    MonoCEA GB 5/04/06 15:30 Page 3 Commissariat à l’énergie atomique e-den A monograph of the Nuclear Energy Directorate Nuclear energy of the future: what research for which objectives? Éditions techniques MonoCEA GB 5/04/06 15:30 Page 2 DEN monographs A monograph of the Nuclear Energy Directorate Commissariat à l’énergie atomique, 31-33, rue de la Fédération 75752 Paris Cedex 15 Tél. : +33-1 40 56 10 00 Scientific comitee Michel Alexandre, Michel Beauvy, Georges Berthoud, Mireille Defranceschi, Gérard Ducros, Yannick Guérin, Yves Limoge, Charles Madic, Gérard Santarini, Jean-Marie Seiler, Pierre Sollogoub, Étienne Vernaz, Research Directors. The following people participated in this work: Fanny Bazile, Patrice Bernard, Bernard Bonin, Jacques Bouchard, Jean-Claude Bouchter, Bernard Boullis, Franck Carré, Jean Cazalet, Alain Marvy, Valérie Moulin, Emmanuel Touron, Yves Terrien. Publishing Supervisor: Philippe Pradel. Editorial Board: Bernard Bonin (Managing Editor), Bernard Bouquin, Martine Dozol, Michel Jorda, Jean-Pierre Moncouyoux, Alain Vallée. Administrator: Fanny Bazile. Editor: Jean-François Parisot. Graphic concept: Pierre Finot. Cover illustration: Véronique Frouard. Correspondence: all correspondence can be addressed to the Editor or to CEA / DEN Direction scientifique, CEA Saclay 91191 Gif-sur-Yvette Cedex. Tél. : + 33-1 69 08 16 75. © CEA Saclay and Groupe Moniteur (Éditions du Moniteur), Paris, 2006 The information contained in this document can be freely reproduced, with the agreement of the Editorial Board and due mention of its origin. MonoCEA GB 5/04/06 15:30 Page 5 Preface After a dazzling start in the 1950s as a promising, inexhaustible, cost-effective energy source, nuclear energy was rejected by majority opinion in several countries in North America and Western Europe three to four decades later, suddenly bringing its development to a halt.
    [Show full text]
  • Feature Article 42 Power 20 Security 27
    February 2016 Volume 59, Number 2 18.00 p. 40 p. 46 16.00 14.00 PUREX $500/kgU 12.00 Advanced PUREX UO $2000, FR-MOX $3750 PUREX $1500/kgU 2 Fuel Cycle 1 10.00 Fuel Cycle 2 8.00 Fuel Cycle 3 Advanced PUREX UO2 $500/kgU, FR-MOX1650 6.00 Fuel Cycle Cost (mill/kWh) Fuel Cycle 4 4.00 Advanced PUREX $3750/kgU Advanced PUREX $1650/kgU 2.00 0.00 $104 $208 $312 $416 $520 Unit Cost Uranium Concentrates ($/kgU) DEPARTMENTS EDITORIAL Feature Article 42 ANS Technical Journals 14 The case for nuclear fuel recycling Backscatter 68 by Melvin R. Buckner and William E. Burchill Calendar 6 Calls for Papers 11 Power 20 Late News 17 Most plants now comply with NRC’s post-Fukushima spent fuel pool instrumenta- Nuclear Notes 4 tion order. NRC reduces oversight of seven reactors. ACRS endorses license issuance People 65 for Duke’s Lee project. NRC dockets petition to define “important to safety.” NRC Recently Published 12 staff advises commission not to revise regulatory framework. Renaissance Watch: An update on developments that may lead to new power reactors. NRC issues con- ADVERTISING firmatory order for violations of spent fuel canister weld-testing procedures at Mon- Direct Answer 54 ticello. Southern California Edison fined $16.7 million by CPUC for unreported talks regarding San Onofre. No new Fermi-2 license renewal hearing; draft second Index to Advertisers 53 supplemental EIS issued for Indian Point. Extra North Anna-3 seismic work com- Employment Ads Begin 58 pleted; other licensing actions.
    [Show full text]
  • Waste Management Transportation Full Page Ad Page C2 What Are We
    Spring 2018 Waste Management Transportation Full Page Ad Page C2 What are we NUCLEAR GLOVEBOXES BECHTEL NATIONAL — GLOVEBOXES We provide the highest grade nuclear glovebox equipment capable of REACTOR SERVICES handling your complex projects. Our gloveboxes have been trusted on high GE HITACHI — STEAM DRYER profile projects such as: River Protection Project vitrification facility, LANL Thanks to our years of experience in nuclear CMRR Project and more. reactor services, we’re prepared to ensure successful project execution for our clients. We continue to supply complex fabrication and Building? machined components to the nuclear industry. WHATEVER YOU NEED. CASKS PROCESS EQUIPMENT ENERGY SOLUTIONS — 3-60 B TRANSPORTATION CASK BECHTEL NATIONAL — MELTERS As an industry leader in manufacturing dry fuel storage and transportation Not only do we fabricate process/transportation casks, we are consistently relied upon to provide quality on-time products equipment, we also provide custom manufacturing for the nuclear industry. equipment for your decommissioning needs. Nuclear gloveboxes, dry fuel storage casks, reactor services — there’s not much we can’t handle. The only question is, what do you need? Whatever it is, you can consider What do you need? Let’s talk about it today. it done with Petersen Inc. A glimpse of our superb manufacturing is only a page away. 800.410.6789 | peterseninc.com We look forward to working with you. Volume 25, Number 1 Spring 2018 Commentary Manufacturing Millenials � � � � � � � � � � � � � � � � � � � 30 Introducing a new generation to the rewards of working with one’s hands. Waste Management Baselining a Spent Nuclear Fuel Cask Shielding Model �� � � � � � � � � � � � � � � � � � � � � � � � � 34 Calculating more accurate dose rates to provide additional flexibility to both nuclear facility designers and operational planners.
    [Show full text]
  • June 15, 1993 Interview with Bertrand Goldschmidt by Avner Cohen
    Digital Archive digitalarchive.wilsoncenter.org International History Declassified June 15, 1993 Interview with Bertrand Goldschmidt by Avner Cohen Citation: “Interview with Bertrand Goldschmidt by Avner Cohen,” June 15, 1993, History and Public Policy Program Digital Archive, From the personal collection of Avner Cohen. https://digitalarchive.wilsoncenter.org/document/113995 Summary: Transcript of Avner Cohen's 1993 interview with Dr. Bertrand Goldschmidt. Goldschmidt was a leading French nuclear scientist who helped develop the PUREX plutonium extraction technique. In this interview, Goldschmidt explains the background of the French role in constructing the Dimona nuclear facility. Credits: This document was made possible with support from the Leon Levy Foundation and Carnegie Corporation of New York (CCNY). Original Language: English Contents: English Transcription Interview with Bertrand Goldschmidt[1] This interview was conducted on 15 June 1993 Interviewer: Dr. Avner Cohen Bertrand Goldschmidt: Think of buying . it wouldn’t have cost them very much, the heavy water[2],[3] produced in Norway. And if we, you see we hid during the war, as it said in that book, those 8 tons of uranium that the Belgians had loaned to Collège de France and by the way, that we never paid and kept. Without the Norwegian heavy water, which was available—we were able to have the first tons produced in Norway after the war— our whole program would have been delayed by three years. And I believe that if the Commissariat [a l'Energie Atomique][4] had loaned its first reactor, let’s say in ’52 or ’53, we wouldn’t have got[ten] the first 5 year plan, which was the plan which allowed us to produce military amounts of plutonium.
    [Show full text]
  • Registration Document 2017
    REGISTRATION DOCUMENT 2017 INCLUDING THE ANNUAL FINANCIAL REPORT MESSAGE FROM THE CHAIRMAN AND CEO 2 2017 KEY FIGURES 4 1 PRESENTATION OF THE GROUP 7 5 RISK FACTORS 83 1.1 History 8 5.1 Risks related to the economic environment 84 1.2 Business overview and Group strategy 11 5.2 Risks related to the Group's operations 85 1.3 Simplifi ed organisation chart of the Group 5.3 Liquidity and market risks 86 at 31 D ecember 2017 14 5.4 Employee-related risks 87 5.5 Risks related to information systems 87 5.6 Legal, regulatory and tax risks 87 2 CORPORATE GOVERNANCE REPORT 15 5.7 Industrial and environmental risks 88 2.1 Board of Directors 17 5.8 Risks related to acquisitions 88 2.2 Compensation and benefi ts in kind allocated by 5.9 Insurance strategy 89 the Company and other Group entities in 2017 to members of the administrative and management bodies in offi ce 30 2.3 Additional information 36 6 FINANCIAL STATEMENTS 91 6.1 Consolidated fi nancial statements 92 6.2 Statutory Auditors report on the consolidated fi nancial statements 137 3 MANAGEMENT REPORT 37 6.3 Parent company fi nancial statements 142 3.1 Business overview 38 3.2 Group results 40 3.3 Assystem SA parent company fi nancial statements 43 INFORMATION ABOUT THE COMPANY 3.4 Compensation of company offi cers 44 7 AND ITS SHARE CAPITAL 167 3.5 Information concerning administrative bodies 44 7.1 General information about the issuer 168 3.6 Information about the Company's capital 44 7.2 Information about the Company’s share capital 171 contents 3.7 Description of main risks and uncertainties
    [Show full text]
  • Uxw 33-35, September 2, 2019
    02 | SEP | 2019 VOL 33 | NO 35 A WEEKLY PUBLICATION OF UXC.COM ® THE LEADING SOURCE FOR TIMELY MARKET INFORMATION UxC Interview with Mr. Tim Gitzel, President and CEO of Cameco Corporation UxC President, Jonathan Hinze, recently had the oppor- tunity to interview Mr. Tim Gitzel, President and Chief Exec- Ux Price Indicators utive Officer (CEO) of Cameco Corporation. Mr. Gitzel gra- ® Weekly Ux U3O8 Price (9/2/19) $25.30 (Unch.) ciously shared with UxC the latest status and plans of his Ux 3-Yr U3O8 Price $28.25 Ux 5-Yr U3O8 Price $32.00 company and his views on the global nuclear markets. Month-end (8/26/19) *Calculated values Jonathan Hinze: Thank you very much for the opportunity to discuss Cameco’s current situation and your views about Spot $25.30 NA Spot $20.00 the future of your company and the nuclear industry. Can you Spot MAP* $25.26 NA Term $16.50 8 O please provide us a brief history of your years at the helm of 3 3-Yr Forward $28.25 EU Spot $19.75 U Cameco and what have been some of the biggest changes at 5-Yr Forward $32.00 Conversion EU Term $16.50 Cameco over this time? Long-Term $32.00 Spot $45.00 Tim Gitzel: NA Price $86.00 SWU Long-Term $47.00 Spot It is a pleasure NA Value* $86.11 NA Spot* $1,160 6 to speak with EUP UF EU Value* $85.86 NA Term* $1,316 you Jonathan. Gitzel: You know, I started in this business in 1979 when I As you know, I was 17 years old.
    [Show full text]