Supplementary Data to Global Risk of Radioactive Fallout After Nuclear
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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. -
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 -
Edf Group Presentation
EDF GROUP PRESENTATION Decommissioning & Waste Treatment Lokala säkerhetsnämnden 9/12/2016 AGENDA 1. EDF GROUP, THE WORLD’S LEADING ELECTRICITY COMPANY 2. OUR AMBITION IN THE NUCLEAR DECOMMISSIONING & WASTE TREATMENT MARKet EDF 2016 I P.2 EDF GROUP, THE WORLD’S LEADING ELECTRICITY COMPANY All electricity-related activities 38.5 MILLION CUSTOMERS — Generation — Transmission & Distribution 158,200 EMPLOYEES — Trading and Sales & Marketing — Energy services €75.0 BILLION SALES EDF ranks: €17.6 BILLION EBITDA among the top 100 largest companies in the world (Fortune Global 500 2014) €12.7 BILLION NET INVESTMENTS EDF is a leader in low-carbon generation: ELECTRICITY GENERATION 102 g/kWh, of which 87% 623.5 TWH carbon-free generation — World’s No. 1 nuclear operator — European No. 1 in generation from renewables — European No. 3 in energy services EDF 2016 I P.3 EDF GROUP IS THE WORLD’S LEADING NUCLEAR FLEET OWNER AND OPERATOR WITH 73 OPERATING UNITS . 72.9 GW installed capacity, 54% of the Group’s net generation capacity . 477.7 TWh generated, 77% of the Group’s output . 58 reactors operated in France, 15 in the UK 5 NEW NUCLEAR PROJECTS . 3 EPR under construction: - 1 in Flamanville (France) - 2 in Taishan (China) . 2 EPR in project phase EDF has a long track record of safe reliable nuclear generation and has a bright future ahead EDF 2016 I P.4 AGENDA 1. EDF GROUP, THE WORLD’S LEADING ELECTRICITY COMPANY 2. OUR AMBITION IN THE NUCLEAR DECOMMISSIONING & WASTE TREATMENT MARKET EDF 2016 I P.5 DECOMMISSIONNING AND WASTE MANAGEMENT ARE KEY -
Study of Acoustic Cavitation Near Metal Surfaces Contaminated by Uranium Ran Ji
Study of acoustic cavitation near metal surfaces contaminated by uranium Ran Ji To cite this version: Ran Ji. Study of acoustic cavitation near metal surfaces contaminated by uranium. Other. Université Montpellier, 2018. English. NNT : 2018MONTS131. tel-02282007 HAL Id: tel-02282007 https://tel.archives-ouvertes.fr/tel-02282007 Submitted on 9 Sep 2019 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. THÈ SE POUR OBTENIR LE GRADE DE DOCTEUR DE L’UNIVERSITÉ DE MONTPELLIER En Chimie Sé parative - Maté riaux et Procé dé s É cole doctorale Sciences Chimiques Balard (ED 459) Unité de recherche Institut de Chimie Sé parative de Marcoule (UMR 5257) Study of Acoustic Cavitation near Metal Surfaces Contaminated by Uranium Pré senté e par Ran JI Le 13 novembre 2018 Sous la direction de Sergueï NIKITENKO Rapport de gestion Devant le jury composé de [Jean-Franç ois DUFÊ CHE, Prof, Université Montpellier] [Pré sident] [Jean-Yves HIHN, Prof, Université de Franche-Comté ] [Rapporteur] 2015 [Laurie BARTHE, MCF, INP Toulouse] [Rapporteur] [Sergueï NIKITENKO, DR, CNRS Montpellier] [Directeur de Thè se] [Claire LE NAOUR, CR, Université Paris Saclay] [Examinateur] [Micheline DRAYE, Prof, Université Savoie Mont Blanc] [Examinateur] [Rachel PFLIEGER, CR, CEA Marcoule] [Encadrant] [Matthieu VIROT, CR, CEA Marcoule] [Encadrant] [Pascal PILUSO, CR, CEA Cadarache] [Invité ] “The unity of inner knowledge and action” [Wang Yangming] Acknowledgements Acknowledgements The doctoral study of the past three years has greatly enriched my experience in academic and personal life. -
Learning from Fukushima: Nuclear Power in East Asia
LEARNING FROM FUKUSHIMA NUCLEAR POWER IN EAST ASIA LEARNING FROM FUKUSHIMA NUCLEAR POWER IN EAST ASIA EDITED BY PETER VAN NESS AND MEL GURTOV WITH CONTRIBUTIONS FROM ANDREW BLAKERS, MELY CABALLERO-ANTHONY, GLORIA KUANG-JUNG HSU, AMY KING, DOUG KOPLOW, ANDERS P. MØLLER, TIMOTHY A. MOUSSEAU, M. V. RAMANA, LAUREN RICHARDSON, KALMAN A. ROBERTSON, TILMAN A. RUFF, CHRISTINA STUART, TATSUJIRO SUZUKI, AND JULIUS CESAR I. TRAJANO Published by ANU Press The Australian National University Acton ACT 2601, Australia Email: [email protected] This title is also available online at press.anu.edu.au National Library of Australia Cataloguing-in-Publication entry Title: Learning from Fukushima : nuclear power in East Asia / Peter Van Ness, Mel Gurtov, editors. ISBN: 9781760461393 (paperback) 9781760461409 (ebook) Subjects: Nuclear power plants--East Asia. Nuclear power plants--Risk assessment--East Asia. Nuclear power plants--Health aspects--East Asia. Nuclear power plants--East Asia--Evaluation. Other Creators/Contributors: Van Ness, Peter, editor. Gurtov, Melvin, editor. All rights reserved. No part of this publication may be reproduced, stored in a retrieval system or transmitted in any form or by any means, electronic, mechanical, photocopying or otherwise, without the prior permission of the publisher. Cover design and layout by ANU Press. Cover image: ‘Fukushima apple tree’ by Kristian Laemmle-Ruff. Near Fukushima City, 60 km from the Fukushima Daiichi Nuclear Power Plant, February 2014. The number in the artwork is the radioactivity level measured in the orchard—2.166 microsieverts per hour, around 20 times normal background radiation. This edition © 2017 ANU Press Contents Figures . vii Tables . ix Acronyms and abbreviations . -
Calculating Nuclear Accident Probabilities from Empirical Frequencies Minh Ha-Duong, V
Calculating nuclear accident probabilities from empirical frequencies Minh Ha-Duong, V. Journé To cite this version: Minh Ha-Duong, V. Journé. Calculating nuclear accident probabilities from empirical frequencies. Environment Systems and Decisions, Springer, 2014, 34 (2), pp.249-258. 10.1007/s10669-014-9499-0. hal-01018478v2 HAL Id: hal-01018478 https://hal.archives-ouvertes.fr/hal-01018478v2 Submitted on 21 Jul 2014 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 - ShareAlike| 4.0 International License Manuscript to appear in Environment, Systems and Decisions CALCULATING NUCLEAR ACCIDENT PROBABILITIES FROM EMPIRICAL FREQUENCIES Minh Ha-Duong et Venance Journé1 2014-04-10 Summary Since there is no authoritative, comprehensive and public historical record of nuclear power plant accidents, we reconstructed a nuclear accident dataset from peer-reviewed and other literature. We found that, in a sample of five random years, the worldwide historical frequency of a nuclear major accident, defined as an INES level 7 event, is 14%. This value is 67 % to have at least one nuclear accident rated at level ≥ 4 on the INES scale. These numbers are subject to uncertainties because the fuzziness of the definition of a nuclear accident. -
Gestior Mr FRO302015 Doc
Gestior Mr FRO302015 Doc. Enreg. 1 F4 If N'TRN INSTITUT D'ECONOMIE ET DE POLITIQUE DE LENERGIE The performing interaction between institutions and technology in the French electronuclear industry Dorninique Finon Carine Staropoli Working Paper (for submission to Industry& Innovation) Grenoble, October 2000 Institut 66conomie et de politique de 16nergie Unit6 mixte de recherche du Centre National de la Recherche Scientifique et de Mniversit6 Pierre Mends France (UFR DGES) IEPE, BP 47, 38040 Grenoble Cedex 09, Tel 04 76 51 42 40 Fax: 04 76 51 45 27 e mail iepeupmf-grenoble.fr ; http:Hwww.upmf-grenob1e.fr/iepe 2 The performing interaction between institutions and technology in the French electronuclear industry. Dominique Finon Carine Staropoli* Among the various traditional "grands programmes" typical of the French public intervention in high-tech industries, the nuclear programme is often considered as one of the major successes. About 60 nuclear reactors have been built between 1970 and 1998. Altogether they generate 80% of the electricity produced by the state-owned monopoly at a competitive cost. Moreover, the French nuclear industry ranks first on the world market of nuclear equipment and services. Such performances are all the more contrasting with those in the other OECD countries, where costs have dramatically increased while many projects never went ahead: since the 1980s a number of electricity companies decided to stop their riskyinvestments in nuclear equipment in many countries. Such a performance is attributable to an appropriate institutional set-up, which has been able to enforce all the technological leaming needed to the implementation of this kind of radical complex and large-sized innovation. -
Gas-Cooled Reactors and Their Applications
IAEA-TECDOC-436 GAS-COOLED REACTORS AND THEIR APPLICATIONS PROCEEDINGS OF A TECHNICAL COMMITTEE MEETING GAS-COOLEN O D REACTOR THEID SAN R APPLICATIONS ORGANIZED BY THE INTERNATIONAL ATOMIC ENERGY AGENCY AND HELD IN JÜLICH, 20-23 OCTOBER 1986 A TECHNICAL DOCUMENT ISSUED BY THE INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1987 GAS-COOLED REACTOR THEID SAN R APPLICATIONS IAEA, VIENNA, 1987 IAEA-TECDOC-436 Printe IAEe th Austri An i y d b a October 1987 FOREWORD Technological development r gas-coolefo s d reactor present a e ar st bein C(>2-cooler gfo larga carrieK n U o e e t scaldth ou d Advancen i e d Gas-Cooled Reactors Higr (AGRsfo h d Temperatur)an e Gas-Cooled Reactors (HTGRs) in the Federal Republic of Germany, United States of America, Japan and USSR. l programmeAl directee sar d towards constructio plantsf o n e Th . mose th t r advancefa y b s i d programmK efforU e th t n witi e h several commercial Hagnox Reactor and Advanced Gas-Cooled Reactor units in operatio d furthean n re constructio th AGR n i s r commissionino n g phase. HTGRs are in operation in the USA and in the Federal Republic of Germany. Othe R specifirHT c wor beins ki g carrieAustrian i t ou d , China and Switzerland. At the IAEA the International Working Group on Gas-Cooled Reactors (IWGGCR bees )ha n establishe 197n i d 8 in order to promote an exchange of information on gas-cooled reactor developmen stimulato t d tan e international cooperation framewore th n I . -
Carbon-14 Source Term CAST
CArbon-14 Source Term CAST WP5 Review of Current Understanding of Inventory and Release of C14 from Irradiated Graphite (D5.5) Author(s): Nelly Toulhout, Ernestas Narkunas, Borys Zlobenko, Daniela Diaconu, Laurent Petit, Stephan Schumacher, Stephane Catherin, Mauro Capone, Werner von Lensa, Gabriel Piña, Steve Williams, Johannes Fachinger, Simon Norris Editor: Simon Norris Date of issue of this report: 15/07/2015 The project has received funding from the European Union’s European Atomic Energy Community’s (Euratom) Seventh Framework Programme FP7/2007-2013 under grant agreement no. 604779, the CAST project. Dissemination Level PU Public X RE Restricted to the partners of the CAST project CO Confidential, only for specific distribution list defined on this document CAST WP5 Review of Current Understanding of Inventory and Release of C14 from Irradiated Graphite (D5.5) CAST – Project Overview The CAST project (CArbon-14 Source Term) aims to develop understanding of the potential release mechanisms of carbon-14 from radioactive waste materials under conditions relevant to waste packaging and disposal to underground geological disposal facilities. The project focuses on the release of carbon-14 as dissolved and gaseous species from irradiated metals (steels, Zircaloys), irradiated graphite and from ion-exchange materials. The CAST consortium brings together 33 partners with a range of skills and competencies in the management of radioactive wastes containing carbon-14, geological disposal research, safety case development and experimental work on gas generation. The consortium consists of national waste management organisations, research institutes, universities and commercial organisations. The objectives of the CAST project are to gain new scientific understanding of the rate of release of carbon-14 from the corrosion of irradiated steels and Zircaloys and from the leaching of ion-exchange resins and irradiated graphites under geological disposal conditions, its speciation and how these relate to carbon-14 inventory and aqueous conditions. -
Manuscript Title in Title Case
Natural Uranium as Alternative Fuel for TEPLATOR Tomáš Peltan University of West Bohemia Univerzitni 8 30100, Pilsen, Czech Republic [email protected] Eva Vilímová, Radek Škoda University of West Bohemia Univerzitni 8 30100, Pilsen, Czech Republic [email protected], [email protected] ABSTRACT The TEPLATOR is an innovative solution for district heating using nuclear energy. It is a special thermal reactor with specific arrangement of the reactor core with 55 fuel assemblies which is moderated and cooled by heavy water and operated at atmospheric pressure with low output temperatures compared to the commercial nuclear power plants. The TEPLATOR DEMO is designed for using irradiated fuel from LWR reactors. In case that the irradiated fuel is not available in terms of high burnup or other reasons, there is a possibility to use SEU or natural uranium as a fuel. This solution is suitable because of the favourable price of natural uranium. This article focuses on development of the alternative suitable fuel for the TEPLATOR, which is based on irradiated fuel reactor core arrangement. It is mainly concerned with neutronic development of the fuel assemblies with appropriate parameters for this application. This article contains various fuel modifications with different time of operation. All calculations were performed by the Monte Carlo code Serpent. 1 INTRODUCTION The TEPLATOR is designed as a new type of reactor for operation with the irradiated VVER-440 fuel assembly with optimal burnup. The reactor will be used as a district heating station. This solution could be interesting for countries, which operate VVER-440 reactors, and which have a large amount of irradiated fuel assemblies stored in long-time storage. -
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M.Bozik (Org and Managerial Aspects of Decom) [Compatibility Mode]
Organizational and Managerial Aspects of Decommissioning after an Accident Miroslav Božik, Peter Gerhart JAVYS, Plc. Slovak Republic JAVYS, Plc. International Experts’ Meeting on Decommissioning and Remediation 1 after a Nuclear Accident, 28.01.-01.02.2013, IAEA, Vienna Content V Short introduction of JAVYS V Organizational and managerial issues related to decommissioning after an accident V Example of A1 NPP decommissioning to demonstrate complexity of the decommissioning process implemented on nuclear facility shut-down after a nuclear accident V Conclusions JAVYS, Plc. International Experts’ Meeting on Decommissioning and Remediation 2 after a Nuclear Accident, 28.01.-01.02.2013, IAEA, Vienna Jadrová a vyra ďovacia spolo čnos ť, a.s. Jadrová a vyra ďovacia spolo čnos ť, a.s. (Nuclear and decommissioning company, Plc. ) Is a state company (Plc.). The Ministry of Economy of the Slovak Republic is the only JAVYS, a.s. shareholder. JAVYS, a.s. activities: V Decommissioning: A1 NPP decommissioning (HWGCR, 1 unit, KS-150) V1 NPP decommissioning (VVER 440, 2 units, V-240) V RAW management: Technologies for RAW processing and treatment Final processing of liquid radioactive waste RAW management National RAW repository V SF management: Interim spent fuel storage V Institutional RAW and detected radioactive material (RAM) management JAVYS, Plc. International Experts’ Meeting on Decommissioning and Remediation 3 after a Nuclear Accident, 28.01.-01.02.2013, IAEA, Vienna Nuclear facilities in JAVYS, a.s. Jadrová a vyra ďovacia spolo čnos ť, a.s. (JAVYS, a.s.) manages following nuclear facilities: JAVYS, Jaslovské Bohunice, A1 NPP, NPP V1, Technologies for RAW management, Interim spent fuel storage JAVYS, Mochovce Final processing of liquid radioactive waste JAVYS, Mochovce, National JAVYS, JAVYS, Trnava RAW repository Bratislava FCC production Headquarter facility JAVYS, Plc. -
Heavy Water Reactors: 1. Physics, Concepts and History
1944-9 Joint ICTP-IAEA Workshop on Nuclear Reaction Data for Advanced Reactor Technologies 19 - 30 May 2008 Heavy Water Reactors: 1. Physics, Concepts and History B.P. Bromley AECL, Chalk River Laboratories Canada Heavy Water Reactors: 1. Physics, Concepts and History Blair P. Bromley Reactor and Radiation Physics Branch AECL – Chalk River Laboratories Joint ICTP-IAEA Workshop on Nuclear Reaction Data for Advanced Reactor Technologies May 26/27, 2008 UNRESTRICTED Outline • Many topics to cover (by no means complete) • Fundamental Physics • Design Options • Physics and Engineering Issues • Review of Conventional HWR Power Reactors – Prototypes / Experiments (Historical) – Commercial Reactors • Present Day and Near Future • Additional Information (see Appendix) – Other HWR concepts. 2 UNRESTRICTED Goals • Better appreciation of heavy water reactors. – Historical review. – We can learn from the past. – Variables change with time. • Better understanding. – Motivation. – How it works. – Design features. – Physics issues, engineering issues. – Long term prospects, implications for future. 3 UNRESTRICTED References • IAEA, Heavy Water Reactors: Status and Projected Development, Tech. Series 407, Vienna, (2002). • IAEA, Directory of Nuclear Reactors, Volumes I to X, (1962 to 1976). • IAEA, Heavy-Water Power Reactors, Proceedings of Symposium, Vienna, 11-15 Sept. 1967 (1968). • IAEA, Heavy Water Lattices: Second Panel Report, Tech. Series No. 20, Vienna, (1963). • AECL, Canada Enters the Nuclear Age, McGill-Queen’s University Press, Montreal, (1997). • AECL, CANDU 6 Technical Outline, TDSI-105, Mississauga, Ontario, Canada, January (1992). 4 UNRESTRICTED A Few Useful References • British Nuclear Energy Society, Steam Generating and Other Heavy Water Reactors, Proc. of Conf. 14-16 May, (1968). • Power Reactor and Nuclear Fuel Development Corporation (Japan), The 9th JUICE Meeting on Heavy Water Reactors, Tokyo, March 11, (1982).