DOCSLIB.ORG

Cost Assessment of Bulgarian Nuclear Newbuild Projects

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Cost Assessment of Bulgarian Nuclear Newbuild Projects Workshop on the Cost Estimation and Cost Analysis of Nuclear Projects and Programmes, Idaho National Laboratory, Idaho Falls, USA, 30 September to 3 October 2019 Cost Assessment of Bulgarian Nuclear Newbuild Projects Ivanova Nina, PhD Head of Finance and Administration Dept. Kozloduy Nuclear Power Plant – New Builds Plc. ‘KOZLODUY NUCLEAR POWER PLANT – NEW BUILDS’ PLC Operational Sunk Average Bookkeeping Opportunity Social Private Investment cost cost Decommissioning cost O&M cost Fuel cost Marginal 10/3/2019 KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS PLC. i. Capital cost ii. Plant operating cost 40% 60% Capital cost Plant operating cost Long-term nuclear waste disposal Nuclear Damage Liabilities Non-Proliferation 10/3/2019 KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS PLC. Rd – cost of debt Re – cost of equity % D-market value of debt E-market value of equity WACC – weighted average capital cost, t - corporate tax rate WACC other +Risk premium nuclear =WACC Nuclear (2) 10/3/2019 KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS PLC. Type of Investor and Cost of Capital Public 10% investors Private investors in 5% regulated markets Private investors in 0% liberalized markets Type of investor Source: Role of Government by [Kee, 2012] Total Investment Costs (TIC) Overnight Construction Financial Capital cost Costs (OCC) costs escalation Engineering, Procurement Owner’s Contingency Interest &Construction Provision During costs Costs (CP) Construction (OC) (EPCC) % 15% 80% 5% 10/3/2019 KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS PLC. • Nuclear fuel and reagents; Fixed • External services; • Nuclear damage 20% insurance, etc. Fuel cycle costs 65% O&M costs • Water used Variable • Materials 15% • Other services, etc. Decommisioning 10/3/2019 KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS PLC. ( + & + + + 1 + ) = = ( (1 + ) )) − ∑ ∗ − - The amount of electricity produced in the∑ year “t” ∗ Construction period - The constant price of electricity (1 + ) - The discount factor for year “t” − - Investment costs in year “t” & - Operations and maintenance costs in year “t” -Fuel costs in year “t” - Carbon costs in year “t” - Decommissioning cost in year “t” Projected nuclear LCOE costs for plants built 2015-2020, $/MWh Source: OECD/IEA-NEA, Projected Costs of Generating Electricity, 2015 Edition, 85% capacity factor 10/3/2019 KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS PLC. Research reactor Kozloduy NPP Belene NPP site - 1957: Bulgaria became one - 1970-1975: Construction and - 1981: Approval for the of the IAEA states–founders commissioning of units 1 and 2 construction of a second - 1957: The Committee for with WWER-440 , model В-230; Bulgarian NPP Peaceful Use of Atomic - 1973-1982: Construction and - 1990: The construction was Energy (CPUAE) has been commissioning of Units 3 and 4 frozen due to lack of financial established with WWER-440 upgraded resources - 1961: Start of operation of model В-230 - 2002: the Government IRT-2000 - 1980-1991: Construction and decided in-principle to restart - 1966: An agreement for commissioning of Units 5 and 6 of the Belene Project commercial reactors for with WWER-1000, model В-320 - 2012: The Council of electricity production was Ministers decided to terminate signed the Belene project 10/3/2019 KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS PLC. In 2012, the Council of Ministers took a decision in principle for construction of a new nuclear power plant at the Kozloduy NPP site. The investment proposal is the construction of a new power plant unit with a generation III or III+ light-water reactor technology with installed capacity ~ 1200 MW, considering the possibility of building a second identical power unit. On May 9th 2012 the project company “Kozloduy NPP - New builds” Plc. was established, with Kozloduy NPP being the sole owner of the capital. The company is part of a vertically integrated holding group – Bulgarian Energy Holding (BEH) with a principle - the Ministry of energy KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS (KNPP-NB) 10/3/2019 KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS PLC. Feasibility stage Technical – economic analysis for the construction of new nuclear unit on the Kozloduy NPP site Investigation and determination of the site for new nuclear capacity at the site of Kozloduy NPP and adjacent Environmental Impact Assessment (EIA) Two main alternatives: (1) maximum use of the equipment ordered for Belene NPP project; or (2) entirely new nuclear reactor project! 10/3/2019 KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS PLC. Issued by: Bulgarian Nuclear Regulatory Agency 10/3/2019 KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS PLC. Feasibility stage Design and construction Decision in Permission Trade principle for use Licence • Council of • National • Minister Ministers Regulatory of • Council of Agency •Energy & Energy • Ministry of Water Ministers Regulatory Regional Commission development Report Decision Operating on merits license 10/3/2019 KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS PLC. A lawsuit for the Atomstroyexport - To be paid and to amount of 1.2 sued NEC for €620 not take any billion euros mln - the cost for actions with it was initiated by the already - To be paid and to Russian side manufactured be sold during 2011 equipment – 2 - To be paid and to after the project nuclear islands be implemented in was canceled a new NPP project 10/3/2019 KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS PLC. -In June 2018, parliament voted to resume the search for investors.; -In May 2019 the government advertised for a strategic investor to participate in the Belene project to build two large reactors, but it said that neither funding guarantees nor long-term electricity sales contracts would be offered; - In August 2019, the energy minister reported that 13 applications for participation had been received, including seven to be a strategic advisor, four to be an electricity customer and/or minority shareholder, and two to be an equipment supplier. KOZLODUY NUCLEAR POWER PLANT - NEW 10/3/2019 BUILDS PLC. - No changes may be made to the safety elements of the design. This is to ensure its licensing; - The owner of the WWER-1000 technology must be involved in obtaining the required licences and permits for the project construction and operation. - The project company must undertake commitments with a supplier of fresh nuclear fuel for the WWER-1000 reactors in accordance with the existing licensing agreements and applicable legislation. - The operator of the built power plant must also be experienced in the operation of VVER-1000 reactors. - The cost of the project construction must not exceed EUR10 billion (USD11 billion) and the commissioning period must be within ten years of signing a shareholders’ agreement. KOZLODUY NUCLEAR POWER PLANT - NEW 10/3/2019 BUILDS PLC. According to the BAS (Bulgarian Academy of Sciences), Bulgaria and the region have a need for 2000 MW of new base power capacity The Belene NPP project is financially viable if: Investment costs - below € 10.5 billion Optimized operational costs Project financing – Debt/Equity ≥ 70/30, interest rate 4,5%; Market Electricity Price - € 68/Mwh ≤ Construction of a new nuclear power plant on the site of Kozloduy NPP with the paid equipment for the terminated project has not been considered The NPP project for newbuild units at the existing NPP site is not cancelled 10/3/2019 KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS PLC. Three options were considered by KNPP-NB - construction of one and two units at the Kozloduy ‘KOZLODUY NUCLEAR POWER PLANT – NEW BUILDS’ PLC NPP site and construction of two units at the Belene site Assumptions: Construction – 10 years, start date Unit 1- 01.01.2019, Unit 2 - 01.01.2020, operation - 60 years, decommissioning - 10 years For result comparing BAS assumptions are used in the three models regarding the exploitation and loading factor of capacities, production, costs of reinvestment and capital repairs, depreciation rate, tax expense, etc. 10/3/2019 KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS PLC. NPP NPP NPP Types of costs € INVESTMENT COSTS, mln BELENE KOZLODUY 7 KOZLODUY 7&8 1&2 Engineering, procurement and construction *** *** *** - Working project *** *** *** - Construction works *** *** *** - Equipment and materials, incl.: *** *** *** Russia, third countries *** *** *** EU supplies *** *** *** - Installation work *** *** *** - Start-up works *** *** *** - Personnel training *** *** *** - Other costs, including: *** *** *** Transport and insurance *** *** *** Insurance *** *** *** Guarantee costs *** *** *** Quality control *** *** *** Management in Russia *** *** *** Vendor's expenditures Vendor's Management of the project *** *** *** Inspection & control *** *** *** Taxes *** *** *** Unforeseen and extraordinary expenses(5%) *** *** *** Total delivery costs *** *** *** Premium for risk and profits (5%) *** *** *** TURNKEY CONTRACT EPC XXXX XXXX XXXX The investment costs of the NPP projects are based on the initial budget of the A - 92 project for Belene NPP (pressurized water reactors, WWER-1000/V466 type). It has been used as a basis for forming an estimated project value to date - max costs 10/3/2019 KOZLODUY NUCLEAR POWER PLANT - NEW BUILDS PLC. NPP NPP NPP Types of € INVESTMENT COSTS, mln KOZLODUY KOZLODUY BELENE costs 7 7&8 1&2 New construction site preparation *** *** *** Nuclear fuel (first charge) *** *** *** Plant connection *** *** *** External physical protection *** *** *** Others *** *** *** Engineering support costs *** *** *** Owner's costs Owner's Total owner's costs XXXX XXXX XXXX Capital
Load more

Recommended publications
  • The Jules Horowitz Reactor Project, a Driver for Revival of the Research Reactor Community
    THE JULES HOROWITZ REACTOR PROJECT, A DRIVER FOR REVIVAL OF THE RESEARCH REACTOR COMMUNITY P. PERE, C. CAVAILLER, C. PASCAL AREVA TA CEA Cadarache - Etablissement d'AREVA TA - Chantier RJH - MOE - BV2 - BP n° 9 – 13115 Saint Paul lez Durance - France CS 50497 - 1100, rue JR Gauthier de la Lauzière, 13593 Aix en Provence cedex 3 – France ABSTRACT The first concrete of the nuclear island for the Jules Horowitz Reactor (JHR) was poured at the end of July 2009 and construction is ongoing. The JHR is the largest new platform for irradiation experiments supporting Generation II and III reactors, Generation IV technologies, and radioisotope production. This facility, composed of a unique grouping of workshops, hot cells and hot laboratories together with a first -rate MTR research reactor, will ensure that the process, from preparations for irradiation experiments through post-irradiation non-destructive examination, is completed expediently, efficiently and, of course, safely. In addition to the performance requirements to be met in terms of neutron fluxes on the samples (5x1014 n.cm-2/sec-1 E> 1 MeV in core and 3,6x1014 n.cm-2/sec-1 E<0.625 eV in the reflector) and the JHR’s considerable irradiation capabilities (more than 20 experiments and one-tenth of irradiation area for simultaneous radioisotope production), the JHR is the first MTR to be built since the end of the 1960s, making this an especially challenging project. The presentation will provide an overview of the reactor, hot cells and laboratories and an outline of the key milestones in the project schedule, including initial criticality in early 2014 and radioisotope production in 2015.
    [Show full text]
  • Decommissioning of Nuclear Facilities in Switzerland – Lessons Learned
    WIR SCHAFFEN WISSEN – HEUTE FÜR MORGEN Fritz Leibundgut :: Decommissioning Officer :: Paul Scherrer Institut Decommissioning of Nuclear Facilities in Switzerland – Lessons learned HRP/IAEA/NEA Decommissioning workshop – February 7, 2017 Overview Basel Germany Aarau/Bern Zürich material sciences nanotechnology radio chemistry hotlab radio pharmacy biology PSI east solar concentrator energy research SwissFEL particle physics proton accelerator neutron source muon source proton therapy PSI west synchrotron light source Page 2 Nuclear installations on the PSI area • (ZWILAG) • AERA with VVA* • Hotlabor • DIORIT* • SAPHIR* • PROTEUS* *Post-operation phase/ Decomm./Dismantling Page 3 SAPHIR: 1957-1993 First reactor in Switzerland; used for isotope production, reactor training, neutron source for various experiments 1955 USA exposed a reactor at the “Atoms for Peace” conference in Geneva 1956 Laying of the cornerstone in Würenlingen 1957 First criticality 1960 Approval by Swiss government 1985 Approval for 10 MW 1993 Final shutdown 2000 Decommissioning ordinance 2008 Dismantling of the pool completed 2015 Cleanout of the KBL (“Kernbrennstofflager”) Page 4 SAPHIR: Status 2016 ENSI-Inspection at 7. of April, 2016 Page 5 DIORIT: 1960-1977 Proprietary Swiss development. Goal was the construction of industrial applicable reactors for material testings and experiments. 1960 Operation with natural uranium and D2O as coolant and moderator. 1966 Uprating from 20 MW to 30 MW. 1972 (after modification): Operation with LEU. 1977 Final shutdown. 1982 Partial dismantling; continued 1988-1993. 1994 Approval of dismantling the reactor. 2005 Asbestos was found interruption until 2009. 2013 Dismantling of biological shielding 2016 Cutting of the „Arbeitsboden“ (22 t activated Fe) 2019 (?) 2. Decommissioning ordinance for greenfield Page 6 DIORIT PSI, 23.10.2016 Page 7 Biol.
    [Show full text]
  • German Research Reactor
    German Research Reactor Back-end Provisions RERTR 2002 San Carlos de Bariloche, Argentina Nov-3/8 Authors: Siegfried Koester/German Federal Ministry of Economics and Technology Gerhard Gruber/RWE NUKEM GmbH On behalf of the German Working Group Back-end for Research Reactors Fuel Cycle History of Half a Century US 'Atoms for Peace Program', President Eisenhower 1953 HEU for peaceful research and development (R&D) First RR built in Germany in the late 1950s US supplied fuel on a lease basis until 1974 Until 1987 fuel sale with option to return spent HEU + LEU fuel 1987-Dec-31: DOE's policy for receipt of FRR SNF expires without prior notice German RR Back-end History 1960s: US Reprocessing, no return of waste 1960/70s: UK Reprocessing, no return of waste 1970s: Belgium + France Reprocessing, no return of waste 1980s: US Reprocessing, no return of waste 1990s: UK Reprocessing, mandatory waste return Current German Back-end Solution 1996 - 2006: Return SNF to US under 'FRR SNF Return Policy' (US-origin) Non-Proliferation: Return of all HEU to the US 2 Promote RR conversion to LEU 10 yrs to provide for national Back-end solutions Establish int. Back-end solutions (e.g. IAEA promotion) German Spent RR Fuel Output Current Reactors (operation time): 'BER-II' (2015), 'FRG-1' (> 2010), 'FRJ-2' (2005?), 'TRIGA-MZ' (>2010), 8 'SUR’ Future Reactors: 'FRM-II' (2003-2033), 'NN' (possibly needed > 2010) Fuels: U-Al, U-Si, U-ZrH, U-PE, U-Mo in future US- and RUS-origin RUS-origin: 'FRM-II' + 'RFR' (shut down) with 1,000 FE leftover
    [Show full text]
  • Institute for Nuclear Research and Nuclear Energy Bulgarian Academy of Sciences
    Institute for Nuclear Research and Nuclear Energy Bulgarian Academy of Sciences 20102010 Present State Future Prospects Short History The Physical Institute of the Bulgarian Academy of Sciences (BAS) was established on 1 July 1946 by academician Georgi Nadjakov who became its first director. JINR, Dubna, was established on 26 March 1956 Acad. G. Nadjakov was signing the Protocol together with 10 representatives of other countries. In the autumn of 1955 the Bulgarian government took a decision to build a research nuclear reactor. In 1962 the Physical Institute of BAS was renamed as the Physical Institute with a Nuclear Experimental Facility. In 1972 it was splited into Institute for Nuclear Research and Nuclear Energy (INRNE) and Institute of Solid State Physics. Mission The Institute for Nuclear Research and Nuclear Energy (INRNE) of the Bulgarian Academy of Sciences is the biggest leading complex centre in Bulgaria for scientific research and applications of the nuclear science and technologies and studies of their interactions with the environment. Vision INRNE guarantees a high quality performance of research and innovation activities, addressed to support important national programs, keeping abreast with the modern scientific achievements. With its long standing experience and active collaboration with leading European and International institutions, INRNE contributes to the progress of the physical science. Since 2003/2004 INRNE BAS is certificated ISO 9001:2000 №3312/0 according to ISO 14001:2004 №357/0 Staff and Budget 14 74 126
    [Show full text]
  • Treatment of Spent Fuels from Research Reactors and Reactor Development Programs in Germany
    TREATMENT OF SPENT FUELS FROM RESEARCH REACTORS AND REACTOR DEVELOPMENT PROGRAMS IN GERMANY K.D. CLOSS XA9949808 Forschungszentrum Karlsruhe, Karlsruhe, Germany Abstract Quite a great number of different types of spent fuel from research reactors and development programs exists in Germany. The general policy is to send back to the USA as long as possible fuel from MTRs and TRIG As of USA origin. An option is reprocessing in Great Britain or France. This option is pursued as long as reprocessing and reuse of the recovered material is economically justifiable. For those fuels which cannot be returned to the USA or which will not be reprocessed, a domestic back-up solution of spent fuel management has been developed in Germany, compatible with the management of spent fuel from power reactors. It consists in dry storage in special casks and, later on, direct disposal. Preliminary results from experimental R&D inves- tigations with research reactor fuel and experience from LWR fuel lead to the conclusion that the direct dis- posal option even for research reactor fuel or exotic fuel does not impose major technical difficulties for the German waste management and disposal concept. 1. RESEARCH AND EXPERIMENTAL REACTORS IN GERMANY At the end of 1997, six research reactors with a power > 100 kW were operating in Germany. These comprise two TRIGA-type reactors, three swimming-pool reactors and one DIDO-type reactor. Moreover, one new research reactor is under construction, the operational start-up of which is expected in 2001. More details of these reactors are given in Table I. In addition to these reactors, there are eight research reactors permanently shut down, some of which have already been dismantled.
    [Show full text]
  • Neutrons for the Nation Discovery and Applications While Minimizing the Risk of Nuclear Proliferation
    Neutrons for the Nation Discovery and Applications while Minimizing the Risk of Nuclear Proliferation A Report by the APS Panel on Public Affairs July 2018 ABOUT APS & POPA AUTHORSHIP Founded in 1899 to advance and diffuse the knowledge of The American Physical Society has sole responsibility for physics, the American Physical Society (APS) is now the nation’s the contents of this report, and the questions, findings, and leading organization of physicists with approximately 55,000 recommendations within. members in academia, national laboratories and industry. APS has long played an active role in the federal government; its members serve in Congress and have held positions such as Science Advisor to the President of the United States, Director ACKNOWLEDGEMENTS of the CIA, Director of the National Science Foundation and We thank Frank Bates, Bill Buyers, David Dean, Alex Glaser, Secretary of Energy. Geoff Greene, Jenny Heimberg, Mark Johnson, John Katsaras, Julia Kornfield, Patrick Lemoine, Dan Neumann, Sean O’Kelly, This report was overseen by the APS Panel on Public Affairs Ray Orbach, Winfried Petry, Roger Pynn, Kate Ross, and (POPA). POPA routinely produces reports on timely topics J. Michael Rowe for their contributions to this report. being debated in government so as to inform the debate with the perspectives of physicists working in the relevant issue areas. PUBLICATION DATE: JULY 2018 REPORT COMMITTEE American Physical Society James Wells, Co-Chair, University of Michigan Physics This report is available under the terms of a Creative Commons Department Attribution 4.0 International License. Sharing and adapting the material for any purpose, even commercial, does not require Julia Phillips, Co-Chair, Sandia National Laboratory prior written permission.
    [Show full text]
  • Assessment of Missions and Requirements for a New U.S. Test Reactor
    Nuclear Energy Advisory Committee Assessment of Missions and Requirements for a New U.S. Test Reactor Draft Report December 2016 i Table of Contents ii Acronyms ANL Argonne National Laboratory ANSTO Australian Nuclear Science and Technology Organisation ATR Advanced Test Reactor BARC Bhabha Atomic Research Centre CAEA China Atomic Energy Authority CEA Commissariat à l’Energie Atomique et aux Energies Alternatives CNEA National Atomic Energy Commission DOD Department of Defense DOE Department of Energy DOE-NE Department of Energy -Office of Nuclear Energy dpa displacements per atom ESAAB Energy Systems Acquisition Advisory Board EBR-II Experimental Breeder Reactor-II GCR Gas-Cooled Reactor GIF Generation IV International Forum FFTF Fast Flux Test Facility FHR Fluoride Salt-Cooled High Temperature Reactor HFIR High Flux Isotope Reactor HTGR High Temperature Gas-cooled reactors HTR-PM High Temperature gas-cooled Reactor Pebble-bed Module IFE Institute for Energy Technology IGCAR Indira Gandhi Centre for Atomic Research IKET Institute for Nuclear and Energy Technologies ININ Instituto Nacional de Investigaciones Nucleare INL Idaho National Laboratory JAEA Japan Atomic Energy Agency (JAEA) KAERI Korea Atomic Energy Research Institute KIT Karlsruhe Institute of Technology LANL Los Alamos National Laboratory LWR Light Water Reactor iii LFR Lead Fast Reactor MITR Massachusetts Institute of Technology Research Reactor MOST Ministry of Science and Technology MSR Molten Salt Reactor MTR Material Test Reactor NAS National Academy of Science NBSR National Bureau of Standards Reactor NEAC Nuclear Energy Advisory Committee NEI Nuclear Energy Institute NRT SC Nuclear Reactor Technology Subcommittee NASA National Aeronautics and Space Administration NNSA National Nuclear Security Administration NRC U.S.
    [Show full text]
  • A National Strategy for Materials Research with Neutron Beams
    DRAFT FOR CONSULTATION A National Strategy for Materials Research with Neutron Beams A discussion paper for the Roundtable Meeting, “Canadian Neutron Initiative: Towards a National Neutron Strategy” To be held as a virtual event, December 15–16, 2020 Updated Dec 10, 2020 1 DRAFT FOR CONSULTATION This Canadian Neutron Initiative (CNI) discussion paper and associated Roundtable Meeting are produced in partnership with CIFAR. We also thank the following sponsors: 2 DRAFT FOR CONSULTATION Contents 1 Executive summary and overview of a national strategy ..................................................................... 5 2 Consultation on the strategy ................................................................................................................ 9 3 The present: A strong foundation for continued excellence .............................................................. 12 3.1 The Canadian neutron beam user community ........................................................................... 12 3.2 McMaster University ................................................................................................................... 16 3.3 Other neutron beam capabilities and interests .......................................................................... 17 4 Forging foreign partnerships ............................................................................................................... 19 4.1 Global renewal of advanced neutron sources ...........................................................................
    [Show full text]
  • The Research Reactor Irt-Sofia: 50 Years After First Criticality
    E4 THE RESEARCH REACTOR IRT-SOFIA: 50 YEARS AFTER FIRST CRITICALITY K. KREZHOV International Institute for Nuclear Research and Nuclear Energy, Bulgarian Academy of Sciences, Sofia, Bulgaria Abstract The design features of the research reactor IRT-2000 in Sofia and accumulated experience in the past prior to the partial dismantling of obsolete reactor systems are outlined. The present status of the ongoing refurbishment to a low power reactor IRT-200 and its planned utilization are briefly described. 1. INTRODUCTION Since early 1956, the Bulgarian government has officially favored the use of nuclear power. In 1957 Bulgaria ratified the Statute of the IAEA and became one of the IAEA states- founders. In June 1957 the Committee for Peaceful Use of Atomic Energy (CPUAE) within the Council of Ministers was established as the specialized state body to promote the nuclear research and applications as well as to control and coordinate the related activities in industry, agriculture, medicine and science. In support to this program the research reactor (RR) IRT- Sofia was contracted. The initial construction of a reactor of the same WWR type as in Poland, Czechoslovakia, Hungary and Rumania that started in 1956 was adapted for the IRT- type of reactor designed and constructed from 1957 to 1961 by the Kurchatov Institute, Moscow. The first chain reaction was accomplished at 20:15 h on September 18, 1961. The official inauguration took place on November 9, 1961. The Reactor underwent several upgrades from initial 500 kW: 1000 kW (1962), 1500 kW (1965) and 2000 kW (IRT-2000) in 1970. The reactor was operated safely with a mixed (LEU-HEU) core for 28 years at power levels agreed upon user demands up to 2000 kW.
    [Show full text]
  • IAEA Nuclear Energy Series Applications of Research Reactors No
    IAEA Nuclear Energy Series IAEA Nuclear No. NP-T-5.3 No. IAEA Nuclear Energy Series Applications of Research Reactors No. NP-T-5.3 Basic Applications of Principles Research Reactors Objectives Guides Technical Reports INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA ISBN 978–92–0–145010–4 ISSN 1995–7807 13-49091_PUB1627_cover_A4.indd 1,3 2014-02-27 08:47:02 IAEA NUCLEAR ENERGY SERIES PUBLICATIONS STRUCTURE OF THE IAEA NUCLEAR ENERGY SERIES Under the terms of Articles III.A and VIII.C of its Statute, the IAEA is authorized to foster the exchange of scientific and technical information on the peaceful uses of atomic energy. The publications in the IAEA Nuclear Energy Series provide information in the areas of nuclear power, nuclear fuel cycle, radioactive waste management and decommissioning, and on general issues that are relevant to all of the above mentioned areas. The structure of the IAEA Nuclear Energy Series comprises three levels: 1 — Basic Principles and Objectives; 2 — Guides; and 3 — Technical Reports. The Nuclear Energy Basic Principles publication describes the rationale and vision for the peaceful uses of nuclear energy. Nuclear Energy Series Objectives publications explain the expectations to be met in various areas at different stages of implementation. Nuclear Energy Series Guides provide high level guidance on how to achieve the objectives related to the various topics and areas involving the peaceful uses of nuclear energy. Nuclear Energy Series Technical Reports provide additional, more detailed information on activities related to the various areas dealt with in the IAEA Nuclear Energy Series. The IAEA Nuclear Energy Series publications are coded as follows: NG — general; NP — nuclear power; NF — nuclear fuel; NW — radioactive waste management and decommissioning.
    [Show full text]
  • Supplement Analysis for the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program
    DOE/EIS-0218-SA-8 SUPPLEMENT ANALYSIS FOR THE FOREIGN RESEARCH REACTOR SPENT NUCLEAR FUEL ACCEPTANCE PROGRAM APRIL 2019 \?f1l ~ : ~ National Nuclear Security Administration U.S. Department of Energy National Nuclear Security Administration Washington, DC Supplement Analysis for the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program TABLE OF CONTENTS Page 1.0 INTRODUCTION AND BACKGROUND ........................................................................................... 1 1.1 Policy on Exemptions ..... ................................................ .... .................................................... 2 1.2 Statement of Intent Between the United States and Japan .................. .. .................... ......... 3 1.3 HEU Shipments ..... .. ............................................................................................................... 3 1.4 Training Research Isotope General Atomics (TRIGA) Fuel .................................... ................ 4 2.0 PURPOSE AND NEED, AND PROPOSED ACTION ............................................................................ 4 2.1 Purpose and Need .................................................... ...................... ....................................... 4 2.2 Proposed Action ............ .. ...................... ....................................................................... .. .... ... 4 2.3 Description of Activities ......................................................................................................... 4 3.0 AFFECTED
    [Show full text]
  • Low Dimensional Neutron Moderators for Enhanced Source Brightness
    Low dimensional neutron moderators for enhanced source brightness Ferenc Mezei 1,2 , Luca Zanini 1, Alan Takibayev 1, Konstantin Batkov 1, Esben Klinkby 1,3 , Eric Pitcher 1 and Troels Sch önfeldt 1,3 1European Spallation Source, ESS AB, PO BOX 176, 22100 Lund, Sweden 2Hungarian Academy of Sciences, Wigner RCF, 1525 Budapest, Pf. 49, Hungary 3DTU Nutech, Technical University of Denmark, DTU Risø Campus, 4000 Roskilde, Denmark Corresponding Author: F. Mezei, European Spallation Source ESS AB, PO BOX 176, 22100 Lund, Sweden, e-mail: [email protected] , Tel:+46 72 179 2039 Abstract In a recent numerical optimization study we have found that liquid para-hydrogen coupled cold neutron moderators deliver 3 – 5 times higher cold neutron brightness at a spallation neutron source if they take the form of a flat, quasi 2-dimensional disc, in contrast to the conventional more voluminous shapes used by now. In the present paper we describe a simple theoretical explanation of this unexpected behavior, which is based on the large difference in para-hydrogen between the values of the scattering mean free path for thermal neutrons (in the range of 1 cm) and its much larger equivalent for cold neutrons. This model leads to the conclusions that the optimal shape for high brightness para- hydrogen neutron moderators is the quasi 1-dimensional tube and these low dimensional moderators can also deliver much enhanced cold neutron brightness in fission reactor neutron sources, compared to much more voluminous liquid D 2 or H 2 moderators currently used. Neutronic simulation calculations confirm both of these theoretical conclusions.
    [Show full text]