NUCLEAR POWER: the Second Encounter
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Radioactive Waste Management Programmes in NEA Member Countries
RADIOACTIVE WASTE MANAGEMENT PROGRAMMES IN OECD/NEA MEMBER COUNTRIES HUNGARY NATIONAL NUCLEAR ENERGY CONTEXT Commercial utilisation of nuclear power in Hungary goes back to several decades. The four VVER 440/213 nuclear units of the Paks Nuclear Power Plant were connected to the electricity grid between 1983 and 1987. In 2015 the NPP generated 15.8 TWh of electricity which accounted for 52.7% of the total electricity generated in that year in Hungary. These data are characteristic for the period of time around 2015. In January 2014 the Government of Hungary and the Government of the Russian Federation concluded an agreement on the cooperation in the field of peaceful use of nuclear energy, which was promulgated in the Act II of 2014. Among others, the Agreement includes the cooperation on the establishment of two VVER-1200 type nuclear power plant units at the Paks site, to be commissioned in 2025, and 2026 respectively. The present country profile of Hungary does not cover the spent fuel and radioactive waste management issues of the new units. Components of Domestic Electricity Production 2015 Source: MAVIR Hungarian Independent Transmission Operator Company Ltd. SOURCES, TYPES AND QUANTITIES OF WASTE Waste classification Most of the radioactive waste in Hungary originates from the operation of the Paks NPP, and much smaller quantities are generated by other (rather institutional, non-NPP) users of radioactive isotopes. The following classification scheme is based on Appendix 2 in the Decree 47/2003 (VIII. 8.) of the Minister of Health on certain issues of interim storage and final disposal of radioactive wastes, and on certain radiohygiene issues of naturally occurring radioactive materials concentrated during industrial activity. -
Reactor Physics Calculations in the Nordic Countries
ESPOO 2003 VTT SYMPOSIUM 230 The eleventh biennial meeting on reactor physics calculations in the Nordic VTT SYMPOSIUM 230 countries was arranged by VTT Processes in Otaniemi, Espoo and on board Tallink´s m/s Romantika on April 9–10, 2003. General reactor physics, calculational methods, a code system adapted for RBMK reactor analyses, and transmutation of nuclear waste were presented by representatives of universities and programme developers. Computer programmes are the most important tools of reactor physics. At the meeting there were presentations of VTT Processes’ new deterministic 3- dimensional radiation transport code MultiTrans and BWR simulator ARES based upon the AFEN model, and also of new features in internationally wellknown codes like CASMO-4E and POLCA (POLCA-T) together with Reactor physics calculations in the Nordic countries results obtained by these programmes. A code for PWR loading pattern search, called LP-fun, is being developed by Westinghouse and others. On the subject of code validation, measurements on SVEA-96+ fuel bundles in the PROTEUS facility had been analyzed with the PHOENIX4 code, reactor scram experiments in the Loviisa and Mochovce VVER reactors using CASMO-4, MCNP4B and HEXTRAN, results of gamma scanning by the PHOENIX4/POLCA7 combination. Some difficulties in predicting the power distribution in the reactor core with sufficiently good accuracy using any of the available code systems were reported by OKG. Heating of non-fuel regions by gamma radiation and neutrons had been investigated using the HELIOS lattice code. Calculational results for heat deposition from gamma radiation in the moderator tank of the Forsmark-1 reactor were reported by Risø. -
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]. -
Nuclear Fuel Optimization and Problem of Xa9953256 Increasing Burnup and Cost Efficiency of Light Water Reactors in Russia
NUCLEAR FUEL OPTIMIZATION AND PROBLEM OF XA9953256 INCREASING BURNUP AND COST EFFICIENCY OF LIGHT WATER REACTORS IN RUSSIA M.I. SOLONIN, Yu. K. BIBLASHCVLI, F.G. RESHETNIKOV, F.F. SOKOLOV, A.A. BOCHVAR All-Russia Research Institute of Inorganic Materials, Moscow, Russia Abstract Brief analysis is given of the results of WWER-1000 and WWER-440 fuel assembly (FA) and fuel rod operation to the average burn-up of 44 and 34 MW-day/kg U, respectively. The reliable operation of the fuel is noted which made it possible to outline the paths of further improvements in their fuel cycles. Based on a series of improvements reactors are being switched on a 4-year cycle; a 5-year cycle is contemplated for the WWER- 440. The fuel cycle of the boiling RBMK reactors is subjected to essential alterations. Specifically, the use of erbium oxide as an integral burnable absorber allows a higher enrichment of uranium and bum-up. To extend the burn-up a new zirconium alloy E-635 is assumed to be used as fuel rod claddings and other FA components; the alloy has higher corrosion and irradiation resistance. INTRODUCTION The current technical level of the PWR and BWR fuel production and the perfected system of the reactor management have allowed to provide the successful operation of PWR NPP to the average burn-up of ~45 MW* day/kg U in all countries of developed nuclear power. The differences in the reliability and FA serviceability as well as in the number of leaky fuel rods are rather small and the attention is usually not focused on this issue. -
Engineering Design of Aries-Iii*
PAPER ENGINEERING DESIGN OF ARIES-HI* O.K. Sze, Argonne National Laboratory, Argonne, IL 60439 C. Wong, General Atomics, San Diego, CA 92138 E. Cheng, TSI Research, Solana Beach, CA 92075 M.E. Sawan, I.N. Sviatoslavsky, J.P. Blanchard, L.A. El-Guebaly, H.Y. Khater, E.A. Mogahed University of Wisconsin, Madison, Wl 53706 P. Gierszewski, Canadian Fusion Fuels Tech. Prog., Mississauga, Ontario, Canada, L5J1K3 R. Hollies, Hollies Fluids Consulting, Pinawa, MB, ROE 1 L0 Canada and the ARIES Team M Z. <*• « (5 E B RECEIVE. AUG 2 6 1993 o M c -5 «3 OSTI Th« uibmitted manuscript has been authored by a contractor of the U. 5. Government under contract No. W-31-109-ENG-38- l Accordingly, the U. S. Government retains a nonexclusive, royalty-free license to publish or reproduce tha published form of this contribution, or allow others to do so, far U. 5. Government purposes. July 1993 •so * Work supported by the U.S. Department of Energy, Office of Fusion Energy, under Contract No. W-31-109-Eng-38. Paper to be presented at the Second Wisconsin Symposium on 3He and Fusion Power, University of Wisconsin, Madison, Wl, July 19-21,1993. DWTFMBUTION OF THIS DOOUMENT IS UNLIMITED ENGINEERING DESIGN OF ARIES-III* D.K. Sze, Argonne National Laboratory, Argonne, IL 60439 C. Wong, General Atomics, San Diego, CA 92138 E. Cheng, TSI Research, Solana Beach, CA 92075 M.E. Sawan, I.N. Sviatoslavsky, J.P. Blanchard, LA. El-Guebaly, H.Y. Khater, E.A. Mogahed University of Wisconsin, Madison, Wl 53706 P. -
Dr. Starr of Atomics International New Head of American Nuclear Societ Y Group Includes Members from 29 Countries Devoted to Ad- Vancement of Nuclear Scienc E
VOL. 1 NO. 2 ATOMICS INTERNATIONAL a division of North American Aviation, Inc . SEPTEMBER 1958 Dr. Starr Of Atomics International New Head Of American Nuclear Societ y Group Includes Members From 29 Countries Devoted To Ad- vancement Of Nuclear Scienc e At the annual meeting in June of the American Nuclear Society (ANS) . Dr. Chauncey Starr, general manager of Atomics International and vice president of North American Aviation, Inc., was elected president of the society to succeed Dr . Leland J . Haworth . Direc- tor of the Brookhaven National Laboratory . The American Nuclear Society was formed in 1955 to advance nuclear science and engineering . to encour- age research . establish scholarships. and to disseminate technical information . Membership of 3,000 Includes 29 Countries The organization's membership of 3 .000 includes about 140 members from 29 countries outside the United States representing many branches of science and technology . Members are associated with educa. tional , governmental, and research institutions, and with government contractors and industrial companies. First Student Award Establishe d In keeping with one of the objectives of the society, the first annual graduate student award has been estab- lished for the most outstanding graduate student work- ing in the nuclear sciences . NEW ANS OFFICERS-At the recent meeting of the URER ; Dr. Chauncey Starr, general manager of Atomics The award is the first of its kind by the society and American Nuclear Societe , new officers elected are : (felt International and vice-president of North American Avia- to right) John A . Swartnut, deputy director of Oak Ridge tion, Inc. PRESIDENT ; and Octave J. -
OECD-IAEA Paks Fuel Project Was Established in 2005 As a Joint Project Between the IAEA and the OECD/NEA
spine: 5.455 mm 81 pages OECD–IAEA Paks Fuel Project Final Report INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA 09-2210-PUB-1389-cover.indd 1 2010-06-29 10:12:33 OECD–IAEA PAKS FUEL PROJECT The following States are Members of the International Atomic Energy Agency: AFGHANISTAN GHANA NIGERIA ALBANIA GREECE NORWAY ALGERIA GUATEMALA OMAN ANGOLA HAITI PAKISTAN ARGENTINA HOLY SEE PALAU ARMENIA HONDURAS PANAMA AUSTRALIA HUNGARY PARAGUAY AUSTRIA ICELAND PERU AZERBAIJAN INDIA PHILIPPINES BAHRAIN INDONESIA POLAND BANGLADESH IRAN, ISLAMIC REPUBLIC OF PORTUGAL BELARUS IRAQ QATAR BELGIUM IRELAND REPUBLIC OF MOLDOVA BELIZE ISRAEL ROMANIA BENIN ITALY RUSSIAN FEDERATION BOLIVIA JAMAICA SAUDI ARABIA BOSNIA AND HERZEGOVINA JAPAN SENEGAL BOTSWANA JORDAN SERBIA BRAZIL KAZAKHSTAN SEYCHELLES BULGARIA KENYA SIERRA LEONE BURKINA FASO KOREA, REPUBLIC OF SINGAPORE BURUNDI KUWAIT SLOVAKIA CAMEROON KYRGYZSTAN SLOVENIA CANADA LATVIA SOUTH AFRICA CENTRAL AFRICAN LEBANON SPAIN REPUBLIC LESOTHO SRI LANKA CHAD LIBERIA SUDAN CHILE LIBYAN ARAB JAMAHIRIYA SWEDEN CHINA LIECHTENSTEIN SWITZERLAND COLOMBIA LITHUANIA SYRIAN ARAB REPUBLIC CONGO LUXEMBOURG TAJIKISTAN COSTA RICA MADAGASCAR THAILAND CÔTE D’IVOIRE MALAWI THE FORMER YUGOSLAV CROATIA MALAYSIA REPUBLIC OF MACEDONIA CUBA MALI TUNISIA CYPRUS MALTA TURKEY CZECH REPUBLIC MARSHALL ISLANDS UGANDA DEMOCRATIC REPUBLIC MAURITANIA UKRAINE OF THE CONGO MAURITIUS UNITED ARAB EMIRATES DENMARK MEXICO UNITED KINGDOM OF DOMINICAN REPUBLIC MONACO GREAT BRITAIN AND ECUADOR MONGOLIA NORTHERN IRELAND EGYPT MONTENEGRO UNITED REPUBLIC EL SALVADOR MOROCCO OF TANZANIA ERITREA MOZAMBIQUE UNITED STATES OF AMERICA ESTONIA MYANMAR URUGUAY ETHIOPIA NAMIBIA UZBEKISTAN FINLAND NEPAL VENEZUELA FRANCE NETHERLANDS VIETNAM GABON NEW ZEALAND YEMEN GEORGIA NICARAGUA ZAMBIA GERMANY NIGER ZIMBABWE 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. -
RECENT DEVELOPMENTS in NUCLEAR SAFETY in HUNGARY April 2019
1 HI LI HUNGARIAN ATOMIC ENERGY AUTHORITY Nuclear Safety Bulletin H-1539 Budapest, P.O. Box 676, Phone: +36 1 4364-800, Fax: +36 1 4364-883, e-mail: [email protected] website: www.haea.gov.hu RECENT DEVELOPMENTS IN NUCLEAR SAFETY IN HUNGARY April 2019 General 2018 annual safety performance assessment of nuclear facilities The HAEA regularly evaluates the safety performance of the operators of nuclear facilities. The main sources of data for the assessment are the regular reports and the event reports of the licensees, the protocols of regulatory inspections including the regular and comprehensive inspections focusing on specific areas, and the reactive inspections. Below we give a short review on the 2018 safety performance assessment. The safety performance data are taken from the quarterly reports of Paks NPP and the semi-annual reports of the other licensees. Paks Nuclear Power Plant Eighteen reportable events occurred in 2018. Eighteen events have been reported by the NPP altogether, all of them were of category „below scale” corresponding to Level-0 on the seven-level International Nuclear Event Scale (INES). 2 There has been no event causing violation of technical operating specification since 2014. On 24 October 2018, the NPP moved to Operating Conditions and Limits (OCL) based on a license by the HAEA. There was no event causing violation of OCL since then. Five automatic reactor protection actuations occurred in 2018. One SCRAM-III and the SCRAM-I actuation were connected to the same event, which was caused by the low water level of steam generators of Unit 3. -
Magnox Corrosion
Department Of Materials Science & Engineering From Magnox to Chernobyl: A report on clearing-up problematic nuclear wastes Sean T. Barlow BSc (Hons) AMInstP Department of Materials Science & Engineering, The University of Sheffield, Sheffield S1 3JD, UK IOP Nuclear Industry Group, September 28 | Warrington, Cheshire, UK Department Of Materials Science & Engineering About me… 2010-2013: Graduated from University of Salford - BSc Physics (Hons) Department Of Materials Science & Engineering About me… 2013-2018: Started on Nuclear Fission Research Science and Technology (FiRST) at the University of Sheffield Member of the Immobilisation Science Laboratory (ISL) group • Wasteforms cement, glass & ceramic • Characterisation of materials (Trinitite/Chernobylite) • Corrosion science (steels) Department Of Materials Science & Engineering Department Of Materials Science & Engineering Fully funded project based PhD with possibility to go on secondment • 3-4 month taught course at Manchester • 2 mini-projects in Sheffield • 3 years for PhD + 1 year write up • Funding available for conferences and training • Lots of outreach work • Site visits to Sellafield reprocessing facility, Heysham nuclear power station & Atomic Weapons Authority Department Of Materials Science & Engineering Fully funded project based PhD with possibility to go on secondment • 3-4 month taught course at Manchester • 2 mini-projects in Sheffield • 3 years for PhD + 1 year write up • Funding available for conferences and training • Lots of outreach work • Site visits to Sellafield reprocessing facility, Heysham nuclear power station & Atomic Weapons Authority Department Of Materials Science & Engineering Department Of Materials Science & Engineering 2017: Junior Project Manager at DavyMarkham Department Of Materials Science & Engineering PhD projects… 4 main projects 1. Magnox waste immobilisation in glass 2. -
Implications of the Accident at Chernobyl for Safety Regulation of Commercial Nuclear Power Plants in the United States Final Report
NUREG-1251 Vol. I Implications of the Accident at Chernobyl for Safety Regulation of Commercial Nuclear Power Plants in the United States Final Report Main Report U.S. Nuclear Regulatory Commission p. o AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources: 1. The NRC Public Document Room, 2120 L Street, NW, Lower Level, Washington, DC 20555 2. The Superintendent of Documents, U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20013-7082 3. The National Technical Information Service, Springfield, VA 22161 Although the listing that follows represents the majority of documents cited in NRC publica- tions, it is not intended to be exhaustive. Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC Office of Inspection and Enforcement bulletins, circulars, information notices, inspection and investi- gation notices; Licensee Event Reports; vendor reports and correspondence; Commission papers; and applicant and licensee documents and correspondence. The following documents in the NUREG series are available for purchase from the GPO Sales Program: formal NRC staff and contractor reports, NRC-sponsored conference proceed- ings, and NRC booklets and brochures. Also available are Regulatory Guides, NRC regula- tions in the Code of Federal Regulations, and Nuclear Regulatory Commission Issuances. Documents available from the National Technical Information Service include NUREG series reports and technical reports prepared by other federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission. -
Fundamentals of Nuclear Reactor Physics
Fundamentals of Nuclear Reactor Physics E. E. Lewis Professor of Mechanical Engineering McCormick School of Engineering and Applied Science Northwestern University AMSTERDAM • BOSTON • HEIDELBERG • LONDON NEW YORK • OXFORD • PARIS • SAN DIEGO SAN FRANCISCO • SINGAPORE • SYDNEY • TOKYO ELSEVIER Academie Press is an imprint of Elsevier Contents Preface xiii 1 Nuclear Reactions 1 1.1 Introduction 1 1.2 Nuclear Reaction Fundamentals 2 Reaction Equations 3 Notation 5 Energetics 5 1.3 The Curve of Binding Energy 7 1.4 Fusion Reactions 8 1.5 Fission Reactions 9 Energy Release and Dissipation 10 Neutron Multiplication 12 Fission Products 13 1.6 Fissile and Fertile Materials 16 1.7 Radioactive Decay 18 Saturation Activity 20 Decay Chains 21 2 Neutron Interactions 29 2.1 Introduction 29 2.2 Neutron Cross Sections 29 Microscopic and Macroscopic Cross Sections 30 Uncollided Flux 32 Nuclide Densities 33 Enriched Uranium 35 Cross Section Calculation Example 36 Reaction Types 36 2.3 Neutron Energy Range 38 2.4 Cross Section Energy Dependence 40 Compound Nucleus Formation 41 Resonance Cross Sections 42 Threshold Cross Sections 46 Fissionable Materials 47 vii viii Contents 2.5 Neutron Scattering 48 Elastic Scattering 49 Slowing Down Decrement 50 Inelastic Scattering 52 3 Neutron Distributions in Energy 57 3.1 Introduction 57 3.2 Nuclear Fuel Properties 58 3.3 Neutron Moderators 61 3.4 Neutron Energy Spectra 63 Fast Neutrons 65 Neutron Slowing Down 66 Thermal Neutrons 70 Fast and Thermal Reactor Spectra 72 3.5 -
Nuclear Power Reactors in the World
REFERENCE DATA SERIES No. 2 2010 Edition Nuclear Power Reactors in the World INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA ISBN 978-92-0-105610-8 ISSN 1011-2642 @ 10-20781_IAEA-RDS-2-30_cover.indd 1 2010-05-26 08:59:05 REFERENCE DATA SERIES No. 2 NUCLEAR POWER REACTORS IN THE WORLD 2010 Edition INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 2010 NUCLEAR POWER REACTORS IN THE WORLD IAEA, VIENNA, 2010 IAEA-RDS-2/30 ISBN 978–92–0–105610–8 ISSN 1011–2642 Printed by the IAEA in Austria July 2010 CONTENTS Introduction . 5 Definitions . 7 Table 1. Reactors in operation, long-term shutdown and under construction, 31 Dec. 2009 . 10 Table 2. Type and net electrical power of reactors connected to the grid, 31 Dec. 2009 . 12 Table 3. Type and net electrical power of reactors under construction, 31 Dec. 2009 . 13 Table 4. Reactor years of experience, up to 31 Dec. 2009 . 14 Table 5. Operating reactors and net electrical power, 1980 to 2009 . 16 Table 6. Nuclear electricity production and share from 1980 to 2009 . 18 Table 7. Annual construction starts and connections to the grid, 1954 to 2009 . 21 Table 8. Number of new reactors connected to the grid and median construction time span . 22 Table 9. Construction starts during 2009 . 24 Table 10. Connections to the grid during 2009 . 25 Table 11. Scheduled connections to the grid during 2009 . 25 Table 12. Reactors planned for construction as known on 31 Dec. 2009 . 26 Table 13. Reactors under construction, 31 Dec. 2009 . 29 Table 14. Reactors in operation, 31 Dec.