Small Reactors with Simplified Design
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Core Safety of Indian Nuclear Power Plants (Npps) Under Extreme Conditions
Sadhan¯ a¯ Vol. 38, Part 5, October 2013, pp. 945–970. c Indian Academy of Sciences Core safety of Indian nuclear power plants (NPPs) under extreme conditions JBJOSHI1,∗, AKNAYAK2, M SINGHAL3 and D MUKHOPADHAYA4 1Homi Bhabha National Institute, Anushaktinagar, Mumbai 400 094, India 2Reactor Engineering Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India 3Nuclear Power Corporation of India Limited, Anushaktinagar, Mumbai 400 0094, India 4Reactor Safety Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India e-mail: [email protected] Abstract. Nuclear power is currently the fourth largest source of electricity produc- tion in India after thermal, hydro and renewable sources of electricity. Currently, India has 20 nuclear reactors in operation and seven other reactors are under construction. Most of these reactors are indigenously designed and built Heavy Water Reactors. In addition, a 300 MWe Advanced Heavy Water Reactor has already been designed and in the process of deployment in near future for demonstration of power production from Thorium apart from enhanced safety features by passive means. India has ambi- tious plans to enhance the share of electricity production from nuclear. The recent Fukushima accident has raised concerns of safety of Nuclear Power Plants world- wide. The Fukushima accident was caused by extreme events, i.e., large earthquake followed by gigantic Tsunami which are not expected to hit India’s coast considering the geography of India and historical records. Nevertheless, systematic investigations have been conducted by nuclear scientists in India to evaluate the safety of the current Nuclear Power Plants in case of occurrence of such extreme events in any nuclear site. -
Liquid Metal Cooled Reactors: Experience in Design and Operation
IAEA-TECDOC-1569 Liquid Metal Cooled Reactors: Experience in Design and Operation December 2007 IAEA-TECDOC-1569 Liquid Metal Cooled Reactors: Experience in Design and Operation December 2007 The originating Sections of this publication in the IAEA were: INIS and Nuclear Knowledge Management and Nuclear Power Technology Development Sections International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 A-1400 Vienna, Austria LIQUID METAL COOLED REACTORS: EXPERIENCE IN DESIGN AND OPERATION IAEA, VIENNA, 2007 IAEA-TECDOC-1569 ISBN 978–92–0–107907–7 ISSN 1011–4289 © IAEA, 2007 Printed by the IAEA in Austria December 2007 FOREWORD In 2002, within the framework of the Department of Nuclear Energy’s Technical Working Group on Fast Reactors (TWG-FR), and according to the expressed needs of the TWG-FR Member States to maintain and increase the present knowledge and expertise in fast reactor science and technology, the IAEA established its initiative seeking to establish a comprehensive, international inventory of fast reactor data and knowledge. More generally, at the IAEA meeting of senior officials convened to address issues of nuclear knowledge management underlying the safe and economic use of nuclear science and technology (Vienna, 17–19 June 2002), there was widespread agreement that, for sustainability reasons for fissile sources and waste management, long-term development of nuclear power as a part of the world’s future energy mix will require the fast reactor technology. Furthermore, given the decline in fast reactor development projects, data retrieval and knowledge preservation efforts in this area are of particular importance. This consensus concluded from the recognition of immediate need gave support to the IAEA initiative for fast reactor data and knowledge presevation. -
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]. -
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. -
Licensing Small Modular Reactors an Overview of Regulatory and Policy Issues
Reinventing Nuclear Power Licensing Small Modular Reactors An Overview of Regulatory and Policy Issues William C. Ostendorff Amy E. Cubbage Hoover Institution Press Stanford University Stanford, California 2015 Ostendorff_LicensingSMRs_2Rs.indd i 6/10/15 11:15 AM The Hoover Institution on War, Revolution and Peace, founded at Stanford University in 1919 by Herbert Hoover, who went on to become the thirty-first president of the United States, is an interdisciplinary research center for advanced study on domestic and international affairs. The views expressed in its publications are entirely those of the authors and do not necessarily reflect the views of the staff, officers, or Board of Overseers of the Hoover Institution. www.hoover.org Hoover Institution Press Publication Hoover Institution at Leland Stanford Junior University, Stanford, California 94305-6003. Copyright © 2015 by the Board of Trustees of the Leland Stanford Junior University The publisher has made this work available under a Creative Commons Attribution-NoDerivs license 3.0. To view a copy of this license, visit http://creativecommons.org/licenses/by-nd/3.0. Efforts have been made to locate the original sources, determine the current rights holders, and, if needed, obtain reproduction permissions. On verification of any such claims to rights in illustrations or other elements reproduced in this essay, any required corrections or clarifications will be made in subsequent printings/editions. Hoover Institution Press assumes no responsibility for the persistence or accuracy of URLs for external or third-party Internet websites referred to in this publication, and does not guarantee that any content on such websites is, or will remain, accurate or appropriate. -
INIS-Mf —14954 CA9600857
i-\ I- S I *• t. -^ INIS-mf —14954 III CA9600857 v // / A ^r^-14 i I ULJ n ^^ ISSN 0S3?-O299 CURRENT ISSUE PAPER i 17 NCIIERNOBYL, THREE MILE ISLAND AND BEYOND; LESSONS FOR ONTARIO? Prepared by: K. Lewis Yeagcr Research C fficer Legij'ative Research Service March 1991 y Ho-sonrch So THKSSSim Nuclear power has been a fact of life in the developed world for two generations. It is v. workhorse supplier of base electricity loads in Ontario, France. Belgium, Japan and many American states. Highly publicized accidents at Chernobyl, and .to.a.lesser..:. extent Three Mile Island, have raised public concern around the world about the safety of nuclear generatin;;, -nations. Since the planning process which will guide the Province's 'power generic:1. for <!ie next 25'years is now under way, it isimportant" that the public and elected officials understand how and why these and other nuclear accidents occurred and whether there are lessons.to.be learned in designing and-, operating CANUU facilities in Ontario. Tilts Current Issue Paper reviews major accidents which nave occurred at commercial and military nuclear facilities, and provides basic background on nuclear power and reactor design features to assist the novice in understanding the very complex technical issues surrounding these events. Above all, the role of human factors in the prevention of potential accident situations is emphasized. ih>- TABLE OF CONTENTS Page No l-xncurivr-: SUMMARY . j INTRODUCTION , ] BACKGROUND 2 . General Principles of Nuclear Power 2 Types of Reactors " " " ~ ' 3 Nuclear Safety Philosophy 5 THREE MILE ISLAND .... 8 The Plant : 8 The Accident ; ft Local Impacts . -
Core Design and Optimization of the High Conversion Small Modular Reactor
Technische Universität München Fakultät für Maschinenwesen Lehrstuhl für Nukleartechnik Core Design and Optimization of the High Conversion Small Modular Reactor Denis Janin Vollständiger Abdruck der von der Fakultät für Maschinenwesen der Technischen Universität München zur Erlangung des akademischen Grades eines Doktor-Ingenieurs (Dr.-Ing.) genehmigten Dissertation. Vorsitzender: Prof. Phaedon-Stelios Koutsourelakis, PhD Prüfer der Dissertation: 1. Prof. Rafael Macián-Juan, PhD 2. Prof. Dr. Jean-Baptiste Thomas Die Dissertation wurde am 08.05.2018 bei der Technischen Universität München eingereicht und durch die Fakultät für Maschinenwesen am 01.11.2018 angenommen. ABSTRACT This research work investigates the design and optimization of the high conversion small modular reactor (HCSMR) core. The HCSMR has a thermal output of 600 MW for 200 MW electrical. It is an integrated PWR with a tightened fuel assembly lattice. The rod-to-rod pitch is 1.15 cm in a hexagonal fuel assembly geometry. As a result the moderation ratio (1.0) is reduced compared to large PWRs (around 2.0) and the HCSMR has an improved ability to convert 238U into 239Pu and use plutonium isotopes more efficiently. The core is loaded with MOX fuel. The HCSMR concept finds its roots both in large high conversion light water reactors and small modular reactor (SMR) concepts. The reduced core size results in an increased neutron leakage rate compared to large cores. This intrinsically supports the core behavior in voided situations. The necessity to introduce fertile fuel materials in the core to keep negative void coefficients is reduced, contributing to the HCSMR safety and limited core heterogeneity. -
Future EQ Perspectives for Russian Global New-Build Projects
Future EQ Perspectives for Russian Global New-Build Projects Natalia Amosova Principal Consultant Lean Six Sigma Black Belt [email protected] +41 79 458 77 13 Prepared for 2020 Curtiss-Wright EQ Technical Meeting November 2020 November, 2020 Curtiss-Wright EQ Technical Meeting 2020 - [email protected] 1 The Water-Water Energy Reactor “VVER” Development and generations + Total number of 106 VVER‘s build since 1960 + Three generations in operation: + VVER-440 + VVER-1000 + VVER-1200 (AES-2006) + Generation III+ under construction: + VVER-1300 (TOI) + New designs developed for future projects: + MIR-1200 + VVER-1500 + VVER-1700 + VVER-600 November, 2020 Curtiss-Wright EQ Technical Meeting 2020 - [email protected] 2 Rosatom Group + Russian government owned corporation, responsible for all nuclear applications + Consists of over 350 specialized companies throughout the whole fuel cycle, of which relevant for us: + Rosatom Overseas (RAOS) - vendor for VVER outside of Russia + AtomEnergoProm (AEP) - designer of the plant + AtomStroyExport (ASE) – main contractor for the international NPP construction + Titan-2 - main contractor for the international NPP construction + AtomEnergoMash (AEM) – Main equipment manufacturer + World leader in todays‘ newbuild portfolio + 28 VVERs under construction (international and domestic) + Total new-build portfolio >130 B. USD November, 2020 Curtiss-Wright EQ Technical Meeting 2020 - [email protected] 3 The Overseas New-Build Projects Overview Rosatom Overseas (RAOS) Plant name Country Unit number