COMMUNICATION Comparisons of Americium, Neodymium, and Europium Complexed by 2,2′–Biphenylenedithiophosphinate

Total Page:16

File Type:pdf, Size:1020Kb

COMMUNICATION Comparisons of Americium, Neodymium, and Europium Complexed by 2,2′–Biphenylenedithiophosphinate COMMUNICATION Comparisons of Americium, Neodymium, and Europium Complexed by 2,2′–Biphenylenedithiophosphinate. Justin N. Cross,1 Joseph A. Macor,1,2 Jeffery A. Bertke,2 Maryline G. Ferrier,1 Gregory S. Girolami,2* Stosh A. Kozimor,1* Joel R. Maassen,1 Brian L. Scott, 1 David K. Shuh,4 Benjamin W. Stein,1 S. Chantal E. Stieber.1,3 Abstract: Advancing understanding of minor actinide (Am, Cm) versus lanthanide coordination chemistry is key for developing advanced nuclear fuel cycles. Owing to difficulties in accessing and handling Am and Cm, few reactivity and spectroscopic comparisons with lanthanides have been performed. Herein, we described the t preparation of (NBu4)Am[S2P( Bu2C12H6)]4 and two isomorphous lanthanide complexes, namely those with similar ionic radii (i.e., NdIII) and that were isoelectronic (EuIII). The results included the first Equation 1. measurement of an Am–S bond length, mean 2.921(9) Å, by single tert-butyl-2,2 ′ -biphenylenedithiophosphinato)metal(III) anions, crystal X-ray diffraction. Structural and spectroscopic comparisons t 1- M[S2P( Bu2C12H6]4 (M = Am, Nd, Eu), enabled the first single- with the EuIII and NdIII complexes revealed subtle electronic III crystal measurement of an Am–S bond distance. Moreover, the differences between Am and the lanthanides. structural results – alongside the UV-vis and fluorescence data – III provocatively, suggested that the Am –S2PR2 interaction was The implementation of advanced nuclear fuel cycles is critically electronically distinct from Ln–S2PR2 bonds within analogous dependent on developing effective methods to process spent coordination environments. fuel. One challenge associated with advancing nuclear fuel Lanthanide complexes of the general formula t reprocessing is associated with separating minor actinides (Am (NBu4)Ln[S2P( Bu2C12H6)]4 (Ln = Nd, Eu) were prepared by salt and Cm) from their 4f-analogues. Owing to difficulties associated metathesis reactions of potassium 4,4′-di-tert-butyl-2,2′- t [4] with conducting macroscopic experiments with Am and Cm, biphenylenedithiophosphinate, KS2P( Bu2C12H6) , with hydrated most insight into minor actinide/lanthanide separation chemistry europium and neodymium trichlorides, followed by addition of comes from microchemical studies, where analyte quantities are tetrabutylammonium chloride, NBu4Cl, Eq 1. As these synthetic more conveniently determined using α, β, and γ–spectroscopy.[1] procedures were quite robust, and routinely provided single This leaves many macroscopic chemical concepts poorly crystals when carried out on either large (> 0.1 g) or small (< understood as there are limited structurally characterized 0.01 g) scales, it seemed reasonable that similar methods would trivalent pairs. [2]. be successful in affording an americium analogue. The Of the many separation strategies that have a high importance of scaling down these reactions cannot be probability for success,[3] those that employ dithiophosphinate overstated, as small-scale synthetic methods accounted for our 243 based extractants are of particular interest. To advance limited inventory of Am and the relatively high radioactivity understanding of these dithiophosphinate separations processes, associated with this isotope, t½ = 7370(40) y. As anticipated, the we recently reported the syntheses of the 4,4′-di-tert-butyl-2,2′- salt metathesis reaction generated the t (NBu )Am[S P(tBu C H )] salt, Scheme 1. This procedure biphenylenedithiophosphinic acid, HS2P( Bu2C12H6), whose aryl 4 2 2 12 6 4 ring orientations were constrained through C–C linkages.[4] We started by dissolving AmO2 in aqueous HCl (6 M), upon which IV III III anticipated – based on previous studies – that constraining the Am reduced to Am . The resulting Am solution was rotameric orientation of the aryl rings provided a mechanism to evaporated to a soft dryness, which left a peach colored residue. control electronic factors that influenced selective binding to 5f Subsequently, the residue was suspendered in ethanol and [5] t treated with ethanolic solutions of KS P(tBu C H ) and NBu Cl. over 4f elements. Moreover, as the HS2P( Bu2C12H6) 2 2 12 6 4 compound was air- and moisture-stable and soluble in a variety For all three complexes, block-shaped single crystals were of common solvents, it provided an excellent opportunity to obtained from slow evaporation of ethanol solutions. Figure 1 compare and contrast minor actinide and lanthanide coordination chemistry with identical dithiophosphinate ligands. As such, this document compares dithiophosphinate coordination chemistry of AmIII (5f 6) with its electronic congener EuIII (4f 6) and its size-matched 4f-analogue, NdIII (ionic radii = [2k,6,7] 1.109 and 1.108 Å). The isolation of the tetrakis(4,4′-di- 1 Los Alamos National Laboratory, Los Alamos, New Mexico 87545 2 University of Illinois at Urbana-Champaign, Urbana, Illinois 61801 3 California State Polytechnic University, Pomona California 91768 4 Lawrence Berkeley National Laboratory, Berkeley California 94720 [email protected], [email protected] t Supporting information for this article is given via a link at the end of Scheme 1. Synthesis of (NBu4)Am[S2P( Bu2C12H6)]4. the document COMMUNICATION Scheme 2. Comparison of the first coordination environments from t 1- t Am[S2P( Bu2C12H6)]4 and Np[S2P( Bu2C12H6)]4. [2k, 6] U, Np and x = 0) versus the metal ionic radii (Figure 2) showed a linear relationship for the EuIII, NdIII, UIV, and NpIV structures. The data was fit with a line whose slope approached unity, 0.89(2), and whose y-intercept [1.95(2) Å] was approximately equal to the S2- ionic radius, 1.84 Å.[6] Interestingly, the observed average Am–S distances of 2.921(9) Å (uncertainty determined as the error of the mean)[9] in t Figure 1. Thermal ellipsoid plot of (NBu4)Am[S2P( Bu2C12H6)]4.Thermal t 1- 1+ Am[S2P( Bu2C12H6)]4 was 0.02 Å shorter than expected from ellipsoids are drawn with 30% probability. NBu4 counter-cation and hydrogen – atoms were omitted. Key: C (gray), P (purple), S (yellow), Am this linear relationship. While tempting to attribute the slightly (pink). shorter Am–S distance to increased Am–S covalency, we refrained as the structural deviations were only marginally t 1- relevant statistically. Instead, these results serve as motivation shows a thermal ellipsoid plot of Am[S2P( Bu2C12H6)]4 , while t 1- for future S K-edge XAS measurements, to determine similar plots for Ln[S2P( Bu2C12H6)]4 (Ln = Nd, Eu) were provided in the SI. Structural metrics from the isomorphous quantitatively the degree of S 3p- and Am 5f-/6d-mixing. III t 1- t The absorption spectra from M [S P( Bu C H )] (M = Eu, (NBu4)M[S2P( Bu2C12H6)]4 (M = Am, Eu, Nd) complexes were 2 2 12 6 4 compared in Table 1. Somewhat unexpectedly, the Nd, Am) were collected from single crystals using a III t 1- III microspectrophotometer (Figure 3). All spectra showed an M [S2P( Bu2C12H6)]4 (M = Eu, Nd, Am) geometries were different than those reported previously for tetravalent intense peak at high energies, likely associated with charge IV t IV transfer transitions. For NdIII and AmIII, weak Laporte forbidden f M [S2P( Bu2C12H6)]4 (M = U, Np) compounds, even though all [11] of these species consisted of f-element ions coordinated by four → f transitions were also present. As observed previously for t 1- [4] (NEt )Eu[S P(C H ) ] ,[12] analogous transitions for S2P( Bu2C12H6) ligands. For instance, Raymond’s Shape8 4 2 6 5 2 4 t 1- routine showed the eight sulfur atoms in the inner sphere of Eu[S2P( Bu2C12H6)]4 were engulfed in the charge transfer band. III t 1- M [S2P( Bu2C12H6)]4 (M = Eu, Nd, Am) formed a distorted bicapped trigonal prism with approximate C2v symmetry, Scheme 2.[8] In contrast, the Shape8 analysis indicated the +4 IV t actinides in M [S2P( Bu2C12H6)]4 (M = U, Np) adopted a distorted trigonal dodecahedral geometry with approximate D2d symmetry. t 1- The Am[S2P( Bu2C12H6)]4 structure enabled the Am–S bond length to be measured for the first time by single crystal X- ray diffraction. The Am–S bond distances varied by approximately 0.1 Å and ranged from 2.887(4) to 2.969(4) Å. These distances agreed well with previously reported EXAFS data from the AmIII complex extracted by bis(2,4,4- trimethylphentyl)dithiophosphinic acid, HS2P[C8H17]2 (cyanex- 301), into kerosene.[10] A plot of mean M–S distances in t x- M[S2P( Bu2C12H6)]4 complexes (M = Eu, Nd, Am and x = 1; M = Table 1. Average bond lengths and angles (with calculated standard [9] t error) in (NBu4)M[S2P( Bu2C12H6)]4 (M = Nd, Eu, Am). Average Bond Lengths (Å) Nd Eu Am M–S 2.941(8) 2.910(9) 2.921(9) M–P 3.525(8) 3.498(8) 3.52(1) Average Bond Angles (°) Nd Eu Am Figure 2. A plot showing the relationship between the M–S Average Bond III t S–M–S 68.6(5) 69.1(5) 68.3(3) distances from (NBu4)M [S2P( Bu2C12H6)]4 (M = Eu, Nd, Am) and S–P–S 112.1(6) 111.4(6) 111.4(8) IV t [4] [6] M [S2P( Bu2C12H6)]4 (M = U, Np) versus the metal ionic radii. COMMUNICATION and 818 nm that could be assigned to 5f → 5f transitions (Figure 3). In accord with previous interpretations of AmIII optical [13] t 1- spectra, the spectrum from Am[S2P( Bu2C12H6)]4 involved III 7 5 2 5 excitations from the Am F0ʹ ground state to the H4ʹ, G2ʹ, D2ʹ, 5 7 7 L6ʹ, F6ʹ, and F4ʹ excited states, respectively. While this interpretation was also described in terms of the free ion, all the AmIII term symbols included a prime mark (ʹ) that served as a reminder to treat the actinides in the so-called intermediate coupling scheme.
Recommended publications
  • 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.
    [Show full text]
  • Advanced Nuclear Power and Fuel Cycle Technologies: Outlook and Policy Options
    Order Code RL34579 Advanced Nuclear Power and Fuel Cycle Technologies: Outlook and Policy Options July 11, 2008 Mark Holt Specialist in Energy Policy Resources, Science, and Industry Division Advanced Nuclear Power and Fuel Cycle Technologies: Outlook and Policy Options Summary Current U.S. nuclear energy policy focuses on the near-term construction of improved versions of existing nuclear power plants. All of today’s U.S. nuclear plants are light water reactors (LWRs), which are cooled by ordinary water. Under current policy, the highly radioactive spent nuclear fuel from LWRs is to be permanently disposed of in a deep underground repository. The Bush Administration is also promoting an aggressive U.S. effort to move beyond LWR technology into advanced reactors and fuel cycles. Specifically, the Global Nuclear Energy Partnership (GNEP), under the Department of Energy (DOE) is developing advanced reprocessing (or recycling) technologies to extract plutonium and uranium from spent nuclear fuel, as well as an advanced reactor that could fully destroy long-lived radioactive isotopes. DOE’s Generation IV Nuclear Energy Systems Initiative is developing other advanced reactor technologies that could be safer than LWRs and produce high-temperature heat to make hydrogen. DOE’s advanced nuclear technology programs date back to the early years of the Atomic Energy Commission in the 1940s and 1950s. In particular, it was widely believed that breeder reactors — designed to produce maximum amounts of plutonium from natural uranium — would be necessary for providing sufficient fuel for a large commercial nuclear power industry. Early research was also conducted on a wide variety of other power reactor concepts, some of which are still under active consideration.
    [Show full text]
  • Preliminary Core Design Studies for the Advanced Burner Reactor Over a Wide Range of Conversion Ratios
    ANL-AFCI-177 Preliminary Core Design Studies for the Advanced Burner Reactor over a Wide Range of Conversion Ratios Nuclear Engineering Division About Argonne National Laboratory Argonne is a U.S. Department of Energy laboratory managed by UChicago Argonne, LLC under contract DE-AC02-06CH11357. The Laboratory’s main facility is outside Chicago, at 9700 South Cass Avenue, Argonne, Illinois 60439. For information about Argonne, see www.anl.gov. Availability of This Report This report is available, at no cost, at http://www.osti.gov/bridge. It is also available on paper to the U.S. Department of Energy and its contractors, for a processing fee, from: U.S. Department of Energy Office of Scientific and Technical Information P.O. Box 62 Oak Ridge, TN 37831-0062 phone (865) 576-8401 fax (865) 576-5728 [email protected] Disclaimer This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor UChicago Argonne, LLC, nor any of their employees or officers, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of document authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof, Argonne National Laboratory, or UChicago Argonne, LLC.
    [Show full text]
  • Small Modular Reactors – Key to Future Nuclear Power Generation in the U.S.1,2
    Small Modular Reactors – Key to Future Nuclear Power Generation in the U.S.1,2 Robert Rosner and Stephen Goldberg Energy Policy Institute at Chicago The Harris School of Public Policy Studies Contributor: Joseph S. Hezir, Principal, EOP Foundation, Inc. Technical Paper, Revision 1 November, 2011 1 The research described in this paper was funded by the U.S. DOE through Argonne National Laboratory, which is operated by UChicago Argonne, LLC under contract No. DE-AC02-06CH1357. This report was prepared as an account of work sponsored by the United States Department of Energy. Neither the United States Government nor any agency thereof, nor the University of Chicago, nor any of their employees or officers, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of document authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof, Argonne National Laboratory, or the institutional opinions of the University of Chicago. 2 This paper is a major update of an earlier paper, July 2011. This
    [Show full text]
  • Nuclear Graphite for High Temperature Reactors
    Nuclear Graphite for High temperature Reactors B J Marsden AEA Technology Risley, Warrington Cheshire, WA3 6AT, UK Abstract The cores and reflectors in modem High Temperature Gas Cooled Reactors (HTRs) are constructed from graphite components. There are two main designs; the Pebble Bed design and the Prism design, see Table 1. In both of these designs the graphite not only acts as a moderator, but is also a major structural component that may provide channels for the fuel and coolant gas, channels for control and safety shut off devices and provide thermal and neutron shielding. In addition, graphite components may act as a heat sink or conduction path during reactor trips and transients. During reactor operation, many of the graphite component physical properties are significantly changed by irradiation. These changes lead to the generation of significant internal shrinkage stresses and thermal shut down stresses that could lead to component failure. In addition, if the graphite is irradiated to a very high irradiation dose, irradiation swelling can lead to a rapid reduction in modulus and strength, making the component friable. The irradiation behaviour of graphite is strongly dependent on its virgin microstructure, which is determined by the manufacturing route. Nevertheless, there are available, irradiation data on many obsolete graphites of known microstructures. There is also a well-developed physical understanding of the process of irradiation damage in graphite. This paper proposes a specification for graphite suitable for modem HTRs. HTR Graphite Component Design and Irradiation Environment The details of the HTRs, which have, or are being, been built and operated, are listed in Table 1.
    [Show full text]
  • Fundamentals of Nuclear Power
    Fundamentals of Nuclear Power Juan S. Giraldo Douglas J. Gotham David G. Nderitu Paul V. Preckel Darla J. Mize State Utility Forecasting Group December 2012 Table of Contents List of Figures .................................................................................................................................. iii List of Tables ................................................................................................................................... iv Acronyms and Abbreviations ........................................................................................................... v Glossary ........................................................................................................................................... vi Foreword ........................................................................................................................................ vii 1. Overview ............................................................................................................................. 1 1.1 Current state of nuclear power generation in the U.S. ......................................... 1 1.2 Nuclear power around the world ........................................................................... 4 2. Nuclear Energy .................................................................................................................... 9 2.1 How nuclear power plants generate electricity ..................................................... 9 2.2 Radioactive decay .................................................................................................
    [Show full text]
  • Zenker, Stephanie F., Ed. Books For
    DOCUMENT RESUME ED 415 506 CS 216 144 AUTHOR Stover, Lois T., Ed.; Zenker, Stephanie F., Ed. TITLE Books for You: An Annotated Booklist for Senior High. Thirteenth Edition. NCTE Bibliography Series. INSTITUTION National Council of Teachers of English, Urbana, IL. ISBN ISBN-0-8141-0368-5 ISSN ISSN-1051-4740 PUB DATE 1997-00-00 NOTE 465p.; For the 1995 edition, see ED 384 916. Foreword by Chris Crutcher. AVAILABLE FROM National Council of Teachers of English, 1111 W. Kenyon Road, Urbana, IL 61801-1096 (Stock No. 03685: $16.95 members, $22.95 nonmembers). PUB TYPE Reference Materials Bibliographies (131) EDRS PRICE MF01/PC19 Plus Postage. DESCRIPTORS *Adolescent Literature; Adolescents; Annotated Bibliographies; *Fiction; High School Students; High Schools; *Independent Reading; *Nonfiction; *Reading Interests; *Reading Material Selection; Reading Motivation; Recreational Reading; Thematic Approach IDENTIFIERS Multicultural Materials; *Trade Books ABSTRACT Designed to help teachers, students, and parents identify engaging and insightful books for young adults, this book presents annotations of over 1,400 books published between 1994 and 1996. The book begins with a foreword by young adult author, Chris Crutcher, a former reluctant high school reader, that discusses what books have meant to him. Annotations in the book are grouped by subject into 40 thematic chapters, including "Adventure and Survival"; "Animals and Pets"; "Classics"; "Death and Dying"; "Fantasy"; "Horror"; "Human Rights"; "Poetry and Drama"; "Romance"; "Science Fiction"; "War"; and "Westerns and the Old West." Annotations in the book provide full bibliographic information, a concise summary, notations identifying world literature, multicultural, and easy reading title, and notations about any awards the book has won.
    [Show full text]
  • PRISM Sodium Fast Reactor Licensing Modernization Project Demonstration
    Modernization of Technical Requirements for Licensing of Advanced Non-Light Water Reactors PRISM Sodium Fast Reactor Licensing Modernization Project Demonstration Project Report Issued Final Authors: Thomas Hicks, Matthew Warner, Gary Miller, Jonathan Li Document Number SC-29980-201 December 2018 Prepared for: U.S. Department of Energy (DOE) Office of Nuclear Energy Under DOE Idaho Operations Office Contract DE-AC07-05ID14517 Issued final by: Jan. 29th, 2019 ________________________________________________ ____________________ Amir Afzali, Next Generation Licensing and Policy Director Date Southern Company Services PRISM Sodium Fast Reactor Licensing Modernization Project Demonstration Disclaimer This report was prepared as an account of work sponsored by an agency of the United States (U.S.) Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, nor Southern Company Services, Inc., nor any of its employees, nor any of its subcontractors, nor any of its sponsors or co-funders, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The
    [Show full text]
  • Progress on Approaches to the Management of Separated Plutonium Position Paper
    Progress on approaches to the management of separated plutonium Position Paper January 2014 Nuclear Materials Doc Ref: SMS/TS/B1-PLUT/002/A Doc ID: 21100718 Progress on approaches to the management of separated plutonium Position Paper January 2014 Contents Executive Summary 3 1 Background 4 2 Programme Outline 5 3 Summary of work 6 3.1 Implementation of reuse as MOX 6 3.2 Alternative proposals to reuse as MOX 7 3.3 Review of non-reuse options 8 3.4 Justification approach 8 4 Summary and outline of next steps 9 Appendix 1 – NDA position on the application of CANDU to the management of separated plutonium 11 Appendix 2 – NDA position on the application of PRISM to the management of separated plutonium 15 Progress on approaches to the management of separated plutonium – Position Paper – v1.0 2 Doc. Ref: SMS/TS/B1-PLUT/002/A Doc ID: 21100718 Progress on approaches to the management of separated plutonium Position Paper January 2014 Executive Summary On completion of reprocessing operations there will be around 140 tonnes of civil separated plutonium in the UK. The UK Government attaches a high priority to developing a policy which will see implementation of a lifecycle solution to put the vast majority of this plutonium beyond reach. This is because of the extensive ongoing security requirements to safely and securely store the material and international non-proliferation objectives to reduce plutonium stocks worldwide. The Nuclear Decommissioning Authority (NDA), as owners of the majority of the material and the body responsible for its ongoing storage, have continued to support the UK Government and the Department of Energy and Climate Change (DECC) as it develops the UK policy on the management of separated plutonium in the UK.
    [Show full text]
  • 1. BACKGROUND to the REVIEW Trap Model for Intensive Purification of the Sodium with a Large Impurities Content
    The fuel made on the base of thorium has a number of favourable features: A REVIEW OF THE UNITED KINGDOM metallic thorium melting point is 1700°C, the first phase transition FAST REACTOR PROGRAMME temperature is 1700°C, thorium oxide melting point is 3200°C; radiation stability of metallic thorium is considerably higher than that J.I. BRAMMAN*, E.R. ADAM**, CG. ALLAN**, of uranium fuel and is near to that of ceramic fuel: 10-15% h.a. burn-up level is experimentally validated; C.V. GREGORY**, H.B. HICKEY* - compatibility of metallic thorium with water is substantially better than *AEA Technology, that of metallic uranium. Risley, Warrington, Cheshire In the nuclear power system sodium cooled fast reactors with passive protection system and featuring high ecological competitiveness will perform **UKAEA Dounreay Nuclear Power Development complex functions: Establishment, Thurso, Caithness - electricity production; - plutonium and uranium-233 output or one of them in proportion or absolute United Kingdom quantity needed by the system; actinides burning out (and also plutonium if needed). Abstract 4.4. Experimental Studies on Actinides Burning-out At the PFR the gross electrical generation for the calendar year 1990 In 1990, the experimental research has been initiated on transuranium was 23,937 MWd with a load factor of 26.2X. These figures are only about element burning out in fast reactors. Fuel specimens containing Am-241, half of the corresponding figures for 1989, mainly as a consequence of an Hp-237, Cm-244 have been installed in the BR-350 reactor fuel subassemblies outage extending from 24 April to 23 November, when a leak in the Reheater for long time irradiation.
    [Show full text]
  • The Integral Fast Reactor (IFR): an Optimized Source for Global Energy Needs
    The Integral Fast Reactor (IFR): An Optimized Source for Global Energy Needs Charles Archambeau1, Randolph Ware2,3, Tom Blees1, Barry Brook4, Yoon Chang5, Jerry Peterson6, Robert Serafin3, Joseph Shuster1, Evgeny Velikhov7,8, Tom Wigley3 1Science Council for Global Initiatives, 2Cooperative Institute for Research in Environmental Sciences, 3National Center for Atmospheric Research, 4University of Adelaide, 5Argonne National Laboratory, 6University of Colorado 7Kurchatov Institute, 8Russian Academy of Sciences February 2011 Contents Abstract........................................................................................................................................... 1 Introduction and Overview ............................................................................................................. 1 Nuclear Power Reactors: History and Status.................................................................................. 5 Pyroprocessing of Spent Nuclear Fuel for Reactor Recycling ....................................................... 6 Integral Fast Reactors: Basic Features............................................................................................ 8 Applications and Costs ................................................................................................................. 12 References..................................................................................................................................... 17 Glossary .......................................................................................................................................
    [Show full text]
  • “Advanced” Isn't Always Better
    SERIES TITLE OPTIONAL “Advanced” Isn’t Always Better Assessing the Safety, Security, and Environmental Impacts of Non-Light-Water Nuclear Reactors “Advanced” Isn’t Always Better Assessing the Safety, Security, and Environmental Impacts of Non-Light-Water Nuclear Reactors Edwin Lyman March 2021 © 2021 Union of Concerned Scientists All Rights Reserved Edwin Lyman is the director of nuclear power safety in the UCS Climate and Energy Program. The Union of Concerned Scientists puts rigorous, independent science to work to solve our planet’s most pressing problems. Joining with people across the country, we combine technical analysis and effective advocacy to create innovative, practical solutions for a healthy, safe, and sustainable future. This report is available online (in PDF format) at www.ucsusa.org/resources/ advanced-isnt-always-better and https:// doi.org/10.47923/2021.14000 Designed by: David Gerratt, Acton, MA www.NonprofitDesign.com Cover photo: Argonne National Laboratory/Creative Commons (Flickr) Printed on recycled paper. ii union of concerned scientists [ contents ] vi Figures, Tables, and Boxes vii Acknowledgments executive summary 2 Key Questions for Assessing NLWR Technologies 2 Non-Light Water Reactor Technologies 4 Evaluation Criteria 5 Assessments of NLWR Types 8 Safely Commercializing NLWRs: Timelines and Costs 9 The Future of the LWR 9 Conclusions of the Assessment 11 Recommendations 12 Endnotes chapter 1 13 Nuclear Power: Present and Future 13 Slower Growth, Cost and Safety Concerns 14 Can Non-Light-Water Reactors
    [Show full text]