Kinetic Simulation, Sensitivity Analysis of Fission Product Activity and Source Term Evaluation for Typical Accident Scenarios in Nuclear Reactors
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Safeguards at Research Reactors: Current Practices, Future Directions
FEATURES Safeguards at research reactors: Current practices, future directions Some new verification measures are being introduced to improve the efficiency and the effectiveness of the Agency's safeguards by Giancarlo /approximately 180 research reactors and crit- immersed in a large pool of water that provides Zuccaro-Labellarte ical assemblies currently are under IAEA safe- both cooling and neutron moderation. The fuel and guards. The vast majority of the research reac- assemblies in the core of a swimming pool reac- Robert Fagerholm tors operate at relatively low power levels (10 tor are normally visible and accessible for safe- megawatts-thermal or lower) and the critical guards measurements. assemblies at virtually zero power.* From a Other types of research reactors operate at safeguards standpoint, this is important since a higher power levels (exceeding 10 megawatts- reactor's power level is a determining factor of thermal). They need more powerful heat its capability to produce plutonium. Along with removal systems and are therefore normally high-enriched uranium (HEU) and uranium- enclosed in core vessels and equipped with 233, plutonium is considered a "direct use" coolant pumps and heat exchangers. The fuel material which could be diverted for the pro- elements in the reactor core at these installa- duction of nuclear weapons. tions are usually not visible or accessible for In this article, the IAEA's safeguards safeguards measurements. implementation at research reactors is Research reactors are widely used for scien- addressed, including aspects related to diver- tific investigations and various applications. sion and clandestine production scenarios and Neutrons produced by research reactors provide main verification activities. -
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 -
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. -
18 IGORR Conference IAEA Workshop on Safety Reassessment
18th IGORR Conference and IAEA Workshop 18th IGORR Conference and IAEA Workshop on Safety Reassessment of Research Reactors in Light of the Lessons Learned from the Fukushima Daiichi Accident, J7-TR-54790 International Conference Centre Sydney Darling Harbour, Sydney, Australia Sunday 3 – Thursday 7 December 2017 Sunday 3 December 17:00 Registration Reception Drinks and canapés Register for the Conference 18th IGORR Conference and IAEA Workshop Monday 4 December 08:20 Opening Session (Room C4.1) Chair: ANSTO Welcome to Country Welcome from ANSTO, IGORR & IAEA 09:00 General Session (Room C4.1) Chairs: David Vittorio & Gilles Bignan Andrea Borio di Tigliole: IAEA activities to support sustainable operation of and access to research reactors Gilles Bignan: The CEA scientific and technical offer as a designated ICERR by the IAEA: First feedback with the prime Affiliates Alexander Tuzov: RIAR as IAEA ICERR: Pilot technical cooperation projects and future prospects Sean O’Kelly: The first 50 years of operation of the ATR at the Idaho National Laboratory Khalid Almarri: A qualitative study for establishing the conditions for the successful implementation of public private partnerships in research reactor project in newcomer contries 10:40 Morning Tea Break (Room C4.4) 11:00 IAEA Workshop (Room C4.1) Chair: David Sears David Sears: IAEA Activities on the safety of Research Reactors Alexander Sapozhnikov: New safety requirements addressing feedback from the Fukushima Daiichi accident Mark Summerfield: Some thoughts on operator intervention arising -
Uncertainty and Sensitivity Analysis for Long-Running Computer Codes: a Critical Review
UNCERTAINTY AND SENSITIVITY ANALYSIS FOR LONG-RUNNING COMPUTER CODES: A CRITICAL REVIEW By MASSACHUSE~s INSTrTUTE' Dustin R. Langewisch OF TECHNOLOGY B.S. Mechanical Engineering and B.S. Mathematics MAR 122010 University of Missouri-Columbia, 2007 L A [ LIBRARIES SUBMITTED TO THE DEPARTMENT OF NUCLEAR SCIENCE AND ENGINEERING IN PARTIAL FULFILLMENT OF THE REQUIREMENTS FOR THE DEGREE OF ARCHIVES MASTER OF SCIENCE IN NUCLEAR SCIENCE AND ENGINEERING AT THE MASSACHUSETTS INSTITUTE OF TECHNOLOGY FEBRUARY 2010 The author hereby grants MIT permission to reproduce and distribute publicly paper and electronic copies of this thesis document in whole or in part in any medium now known or hereafter created. Copyright 0 Massachusetts Institute of Technology All rights reserved. Signature of Author: "-1epartment of Nuclear Science and Engineering January 28, 2010 Certified by: Dr. Gofge E p-p'stolakis, Thesis Supervisor KEPCO Professor of Nuclear Science and Engineering Professor of Engineering Systems Certified by: Don d Helton, Thesis Reader of ear Regulatory Research a. Regulatory Commission Accepted by: Dr. Jacquelyn C. Yanch Chair, Department Committee on Graduate Students UNCERTAINTY AND SENSITIVITY ANALYSIS FOR LONG-RUNNING COMPUTER CODES: A CRITICAL REVIEW Dustin R. Langewisch SUBMITTED TO THE DEPARTMENT OF NUCLEAR SCIENCE AND ENGINEERING IN PARTIAL FULFILLMENT OF THE REQUIREMENTS FOR THE DEGREE OF MASTER OF SCIENCE IN NUCLEAR SCIENCE AND ENGINEERING AT THE MASSACHUSETTS INSTITUTE OF TECHNOLOGY FEBRUARY 2010 Abstract This thesis presents a critical review of existing methods for performing probabilistic uncertainty and sensitivity analysis for complex, computationally expensive simulation models. Uncertainty analysis (UA) methods reviewed include standard Monte Carlo simulation, Latin Hypercube sampling, importance sampling, line sampling, and subset simulation. -
The Nuclear Illustrative Programme of the Commission (PINC), and Is a Collection of Factual Data Gathered from Several Sources
EUROPEAN COMMISSION Brussels, 4.4.2016 SWD(2016) 102 final COMMISSION STAFF WORKING DOCUMENT Accompanying the document Communication from the Commission Nuclear Illustrative Programme presented under Article 40 of the Euratom Treaty for the opinion of the European Economic and Social Committee {COM(2016) 177 final} EN EN Table of figures ...................................................................................................................................... 3 1 Introduction ................................................................................................................................... 4 1.1 Overview of the European nuclear industry ............................................................................ 4 2 The front-end of the nuclear fuel cycle ........................................................................................ 6 2.1 Demand for natural uranium .................................................................................................... 6 2.2 Conversion ............................................................................................................................... 7 2.3 Enrichment .............................................................................................................................. 7 2.4 Fuel fabrication ........................................................................................................................ 8 3 Nuclear new build ....................................................................................................................... -
Engineering Science Ph.D. in Nuclear Engineering / Nuclear Science and Technology Syllabus for Written Test Institute for Plas
Engineering Science Ph.D. in Nuclear Engineering / Nuclear Science and Technology Syllabus for Written Test Institute for Plasma Research 2019 1. BASIC CONCEPTS IN NUCLEAR PHYSICS: Nuclear constituents – charge, mass, shape, and size of nucleus, Binding energy, packing fraction, nuclear magnetic moment, saturation and short range nuclear forces, Radioactivity – Laws of radioactive decay, half life, mean life, specific activity, partial radioactive decay, successive disintegration, α decay: Barrier penetration, β decay: Fermi theory, selection rules, parity non-conservation, γ decay of excited states. Nuclear models – single particle shell model, evidence and limitations of shell model, liquid drop model : Introduction, assumptions, semi-empirical mass formula 2. NUCLEAR DETECTORS, ACCELERATORS AND REACTORS Types of detectors, Geiger-Mueller counter, Scintillation counter, classification of accelerators, Cyclotron, Betatron. Nuclear Reactor – Basic principle, classification, constituent parts, Heterogeneous reactor, Swimming pool reactor, Breeder reactor, Heavy water cooled and moderated CANDU type reactors, Gas cooled reactors. General considerations about reactor physics, engineering requirements- Description of the neutron distribution: fluxes, currents, and sources-Nuclear data, cross sections, and reaction rates- Basic scheme of nuclear system modeling methods-Deterministic modeling of nuclear systems-Neutron balance (conservation) equations. Spent fuel - light water reactor, light water reactor MOX, fast reactor MOX Radiotoxicity -
Research Reactors: Addressing Challenges and Opportunities To
3.57 mm spine Research Reactors: Addressing Challenges and Opportunities to Ensure Effectiveness and Sustainability Summary of an International Conference Buenos Aires, Argentina, 25–29 November 2019 INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA RESEARCH REACTORS: ADDRESSING CHALLENGES AND OPPORTUNITIES TO ENSURE EFFECTIVENESS AND SUSTAINABILITY The Agency’s Statute was approved on 23 October 1956 by the Conference on the Statute of the IAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The Headquarters of the Agency are situated in Vienna. Its principal objective is “to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world’’. PROCEEDINGS SERIES RESEARCH REACTORS: ADDRESSING CHALLENGES AND OPPORTUNITIES TO ENSURE EFFECTIVENESS AND SUSTAINABILITY SUMMARY OF AN INTERNATIONAL CONFERENCE ORGANIZED BY THE INTERNATIONAL ATOMIC ENERGY AGENCY AND HOSTED BY THE GOVERNMENT OF ARGENTINA THROUGH THE NATIONAL ATOMIC ENERGY COMMISSION AND HELD IN BUENOS AIRES, 25–29 NOVEMBER 2019 INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 2020 COPYRIGHT NOTICE All IAEA scientific and technical publications are protected by the terms of the Universal Copyright Convention as adopted in 1952 (Berne) and as revised in 1972 (Paris). The copyright has since been extended by the World Intellectual Property Organization (Geneva) to include electronic and virtual intellectual property. Permission to use whole or parts of texts contained in IAEA publications in printed or electronic form -
Tổng Luận: Năng Lượng Hạt Nhân
TỔNG LUẬN THÁNG 04/2011 LỘ TRÌNH PHÁT TRIỂN CÔNG NGHỆ NĂNG LƢỢNG HẠT NHÂN VÀ DỰ BÁO TRIỂN VỌNG TRONG TƢƠNG LAI 1 CỤC THÔNG TIN KHOA HỌC VÀ CÔNG NGHỆ QUỐC GIA Địa chỉ: 24, Lý Thƣờng Kiệt. Tel: 8262718, Fax: 9349127 Ban Biên tập: TS. Tạ Bá Hưng (Trƣởng ban), ThS. Cao Minh Kiểm (Phó trƣởng ban), ThS. Đặng Bảo Hà, Nguyễn Mạnh Quân, ThS. Nguyễn Phương Anh, Phùng Anh Tiến. MỤC LỤC Trang LỜI GIỚI THIỆU 1 I. I. NĂNG LƢỢNG HẠT NHÂN: MỘT SỐ KHÁI NIỆM CƠ BẢN 3 1. Năng lượng hạt nhân: tổng hợp, phân hạch hạt nhân 3 2. Công nghệ lò phản ứng hạt nhân, chu trình 6 3. Chất thải 8 4. An toàn hạt nhân, sự cố hạt nhân và phóng xạ 10 5. Điều phối quốc tế về năng lượng hạt nhân 18 II. SỰ PHÁT TRIỂN CÔNG NGHỆ NĂNG LƢỢNG HẠT NHÂN 22 1. Công nghệ lò phản ứng hạt nhân thế hệ I, II và III 22 21 2. Công nghệ năng lượng hạt nhân thế hệ IV và lộ trình phát triển 33 30 3. Công nghệ chu trình nhiên liệu hạt nhân 48 III. HIỆN TRẠNG VÀ DỰ BÁO TRIỂN VỌNG NĂNG LƢỢNG HẠT 51 NHÂN THẾ GIỚI 1. Hiện trạng năng lượng hạt nhân thế giới 51 2. Dự báo về triển vọng năng lượng hạt nhân toàn cầu 56 KẾT LUẬN 61 TÀI LIỆU THAM KHẢO 64 2 LỜI GIỚI THIỆU Dân số thế giới được cho là sẽ tăng từ 6 tỷ người hiện nay lên mức 9 tỷ vào năm 2050, và mọi người đều ra sức nỗ lực để có được chất lượng cuộc sống tốt hơn. -
Progress Report for Period Ending December 1961 Department of Reactor Physics AKTIEBOLAGET ATOMENERGI
AE-79 Progress Report for Period Ending Cs December 1961 Department of Reactor Physics AKTIEBOLAGET ATOMENERGI STOCKHOLM SWEDEN 1962 ÅE-79 AKTIEBOLAGET ATOMENERGI Department for Reactor Physics Foreword; This is the second Progress Report from the Department for Reactor Physics of Aktiebolaget Atomenergi, which is issued for the information of institutions and persons interested in the progress of the work. In this report the activities of the General Physics Section have been included, since this section nowadays belongs to the department. This is merely an informal progress report, and the results and data presented must be taken as preliminary. Final results will be sub- mitted for publication either in the regular technical journals or as monographs in the series AE-reports. B Tell Editor Printed and distributed in August 1962 2. LIST OF CONTENTS Page Foreword Plasma Physics; Erik Karlson 5 Experimental Plasma Physics 5 - Rotating Plasma 5 - Plasma Acceleration 6 - Plasma Resonance 6 Theoretical Reactor Physics Section: Bengt Pershagen 8 Project Calculations 8 - R3-Ågesta • 8 - R4-Mar viken 9 - PHWR 10 - Boiling and Superheating Reactor Design Study 10 Research and Development 11 - Lattice Calculation Methods 11 - Fast Neutron Spectrum and Group Constants 11 - Heterogeneous Methods 12 - Fuel Cycle Code 13 - Control Rod Theory 13 - Reactor Kinetics and Stability 13 - Fast Reactor Physics 14 - Neutron Slowing-down and Thermalization 15 Experimental Reactor Physics Section; Rolf Pauli & Eric Hellstrand 18 Reactor Physics I 18 - Experimental Facilities 18 - Substitution Technique 19 - R3 Fuel Assemblies 20 - Fuel for the R4 Project 20 - Uniform UO? Lattices 21 - Fuel for the HBWR (Halden Reactor) 21 - Fuel Exchanged with the SRL 21 - Miscellaneous 22 3. -
Atomic Energy of Canada Limited
Sudan Academy of Sciences Atomic Energy Council ^ rr* /■ i A thesis submitted in partial fulfillment of the requirements for the Degree of Master of Science in Nuclear Science By Hisham Mirghani Dirar B.Sc. University of Khartoum. 1999 Supervisor Prof. Adam Sam June 2012 Sudan Academy of Sciences Atomic Energy Research Council Examination Committee h n \ i i Title Name Signature i A s 1 4 V ■■ , \ r i External Examiner Dr.Siddig Abdalla Talha 1 j - ! , i i S 1 i Supervisor Prof.Adam Khatir Sam . S- • T i 1 -1 Date of Examination: 27lh September, 2012 Dedication I dedicate this thesis to my family, fo r their constant support \ S and unconditional >!• * i love. I Acknowledgem ents First of all I would like to thank God for the grace strength provided to me for completing this thesis. I take immense pleasure in thanking P r o f . A d a m S a m from Sudan Atomic Energy Commission (SAEC), who has chosen the topic, for having permitted me to perform my master’s thesis. P r o f . S a m is a good advisor and one of the smartest people I know. I am also very grateful to D r.Farouk H abbani from The Department of Physics in University of Khartoum for his scientific advice and knowledge and many insightful discussions and suggestions. Also, a special thanks to M r . R a n i O s a m a from (SAEC) for his valuable information. Finally, I would like to express my appreciation and gratitude to my family, especially my parents, for their support, encouragement and advice during my studies and during the realization of this thesis.