Xii Plan Proposals Report of the Working Group
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Development of a Solvent Extraction Process for Group Actinide Recovery from Used Nuclear Fuel
THESIS FOR THE DEGREE OF DOCTOR OF PHILOSOPHY Development of a Solvent Extraction Process for Group Actinide Recovery from Used Nuclear Fuel EMMA H. K. ANEHEIM Department of Chemical and Biological Engineering CHALMERS UNIVERSITY OF TECHNOLOGY Gothenburg, Sweden, 2012 Development of a Solvent Extraction Process for Group Actinide Recovery from Used Nuclear Fuel EMMA H. K. ANEHEIM ISBN 978-91-7385-751-2 © EMMA H. K. ANEHEIM, 2012. Doktorsavhandlingar vid Chalmers tekniska högskola Ny serie Nr 3432 ISSN 0346-718X Department of Chemical and Biological Engineering Chalmers University of Technology SE-412 96 Gothenburg Sweden Telephone + 46 (0)31-772 1000 Cover: Radiotoxicity as a function of time for the once through fuel cycle (left) compared to one P&T cycle using the GANEX process (right) (efficiencies: partitioning from Table 5.5.4, transmutation: 99.9%). Calculations performed using RadTox [HOL12]. Chalmers Reproservice Gothenburg, Sweden 2012 Development of a Solvent Extraction Process for Group Actinide Recovery from Used Nuclear Fuel EMMA H. K. ANEHEIM Department of Chemical and Biological Engineering Chalmers University of Technology Abstract When uranium is used as fuel in nuclear reactors it both undergoes neutron induced fission as well as neutron capture. Through successive neutron capture and beta decay transuranic elements such as neptunium, plutonium, americium and curium are produced in substantial amounts. These radioactive elements are mostly long-lived and contribute to a large portion of the long term radiotoxicity of the used nuclear fuel. This radiotoxicity is what makes it necessary to isolate the used fuel for more than 100,000 years in a final repository in order to avoid harm to the biosphere. -
Analysis of Zirconium and Nickel Based Alloys and Zirconium Oxides
NET318_proof ■ 22 February 2017 ■ 1/7 Nuclear Engineering and Technology xxx (2017) 1e7 Available online at ScienceDirect 65 66 1 67 2 Nuclear Engineering and Technology 68 3 69 4 70 5 journal homepage: www.elsevier.com/locate/net 71 6 72 7 73 8 74 9 Original Article 75 10 76 11 Analysis of Zirconium and Nickel Based Alloys and 77 12 78 13 Zirconium Oxides by Relative and Internal 79 14 80 15 81 16 Monostandard Neutron Activation Analysis 82 17 83 18 Q1 Methods 84 19 85 20 * 86 21 a b, a,1 Q15 Q2Amol D. Shinde , R. Acharya , and A.V.R. Reddy 87 22 88 Q3 a Analytical Chemistry Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India 23 89 b Radiochemistry Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India 24 90 25 91 26 92 article info abstract 27 93 28 94 29 Article history: Background: The chemical characterization of metallic alloys and oxides is conventionally 95 30 Received 9 March 2016 carried out by wet chemical analytical methods and/or instrumental methods. Instru- 96 31 Received in revised form mental neutron activation analysis (INAA) is capable of analyzing samples nondestruc- 97 32 1 August 2016 tively. As a part of a chemical quality control exercise, Zircaloys 2 and 4, nimonic alloy, and 98 33 99 34 Accepted 19 September 2016 zirconium oxide samples were analyzed by two INAA methods. The samples of alloys and Available online xxx oxides were also analyzed by inductively coupled plasma optical emission spectroscopy 100 35 101 (ICP-OES) and direct current Arc OES methods, respectively, for quality assurance pur- 36 102 Keywords: poses. -
The Actinide Research Quarterly Is Published Quarterly to Highlight Recent Achievements and Ongoing Programs of the Nuclear Materials Technology Division
1st quarter 2000 TheLos Actinide Alamos National Research Laboratory N u c l e a r M aQuarterly t e r i a l s R e s e a r c h a n d T e c h n o l o g y a U.S. Department of Energy Laboratory Organizers Issue an Invitation to In This Issue Plutonium Futures 1 —The Science Organizers Issue an Invitation to Plutonium Futures —The Science The second of a series of international con- have an exciting collection of some 180 invited ferences on plutonium will be held in Santa Fe, and contributed papers with topics ranging 2 NM, this summer, July 10–13. It follows the very broadly in materials science, transuranic 238Pu Aqueous highly successful 1997 conference, “Plutonium waste forms, nuclear fuels and isotopes, separa- Processing Line Will Futures - The Science,” which attracted over 300 tions, actinides in the environment, detection Provide New NMT participants representing 14 countries. The U.S. and analysis, actinide compounds and com- Capability participants, who made up about 70 percent of plexes, and condensed matter physics of ac- the total participants, came from Department of tinides. These papers, presented in separate 4 Energy national laboratories and a score of uni- oral and poster sessions, will give attendees a Editorial: versities and industries. As in 1997, the confer- chance to learn about current research outside Transactinium ence is sponsored by the Los Alamos National of their particular specialties and provide an Science Needs Laboratory in cooperation with the American opportunity for interdisciplinary discussions Educational Nuclear Society. -
India's Stocks of Civil and Military Plutonium and Highly Enriched Uranium, End 2014
PlutoniumPlutonium andand HighlyHighly EnrichedEnriched UraniumUranium 20152015 INSTITUTEINSTITUTE FOR FOR SCIENCE SCIENCE AND AND INTERNATIONAL INTERNATIONAL SECURITY SECURITY India’s Stocks of Civil and Military Plutonium and Highly Enriched Uranium, End 20141 By David Albright and Serena Kelleher-Vergantini November 2, 2015 1 This report is part of a series on national and global stocks of nuclear explosive materials in both civil and military nuclear programs. This work was generously funded by a grant from the Nuclear Threat Initiative (NTI). This work builds on earlier work done at ISIS by one of the authors. 440 First Street NW, Suite 800, Washington, DC 20001 TEL 202.547.3633 Twitter @TheGoodISIS E-MAIL [email protected] • www.isis-online.org Contents Summary .............................................................................................................................................. 2 1. India’s Civil Plutonium Stockpile .................................................................................................... 3 1.1 Civil Plutonium Production ........................................................................................................ 3 1.2 Plutonium Separation ................................................................................................................. 5 1.2.1 India’s Fast Breeder Reactors .............................................................................................. 6 1.3 Unirradiated Plutonium Inventory ............................................................................................. -
Preparation and Submission of a Manuscript for the Proceedings
IAEA-TM-38728 (2010) OPERATION AND UTILIZATION OF INDIAN RESEARCH REACTOR DHRUVA SAMIR KUMAR MONDAL Bhabha Atomic Research Centre, Mumbai, India [email protected] 1. INTRODUCTION The role of research reactors for the development of the nuclear programme of any country is well established. Research reactors are utilized to produce radioisotopes and offer irradiation facilities for testing various nuclear fuel and structural materials. Apart from providing a large volume neutron source for carrying out a variety of experiments, the research reactor forms the basic training facility for grooming scientists and engineers for various aspects of a nuclear programme. India’s fifth research reactor Dhruva, which became critical on 8 August 1985, is a natural uranium fuelled, heavy water moderated and cooled thermal research reactor with a rated power level of 100 MW and a maximum thermal neutron flux of 1.8×1014 cm-2s-1. The indigenously designed and built reactor is located at the Bhabha Atomic Research Centre (BARC) in Trombay. Dhruva is a product of technological initiatives taken in India during the 1970s with a totally indigenous effort when a need was felt for a research reactor having a high neutron flux to meet the growing demands of research and development. In addition, large scale production of radioisotopes with high specific activity was possible with the commissioning of Dhruva. This high flux reactor was designed and built with many innovative features which were being considered for our power reactors at that time. The reactor has a vertical core and employs natural metallic uranium in seven-pin cluster fuel assemblies installed in Zircaloy guide tubes in a stainless steel reactor vessel. -
Chapter 2 Proposed Action and Alternatives
Final Environmental Assessment for Actinide Chemistry and Repository Science Laboratory CHAPTER 2 PROPOSED ACTION AND ALTERNATIVES The WIPP facility, in addition to serving its primary mission as a TRU waste disposal site, needs to perform a variety of actinide chemistry experiments to (1) support WIPP’s recertification efforts, (2) address scientific questions important to WIPP, (3) improve TRU waste characterization techniques, and (4) improve DOE’s understanding of how the waste interacts with the natural environment in order to better understand waste isolation performance. In the past, WIPP-related actinide chemistry experiments have taken place at DOE laboratory facilities at other DOE sites such as LANL. However, due to reductions in travel budgets and additional security requirements being imposed on DOE weapons laboratories, DOE believes it would be better able to maintain the budget, schedule, and quality of experiments conducted in support of the WIPP program if they were performed in Carlsbad. DOE is preparing this document to inform decision makers about the potential environmental impacts of the actinide chemistry experiments associated with the Proposed Action, one alternative laboratory location, and a no action alternative, each of which are described in more detail in this chapter. Under the Proposed Action, DOE would construct and operate the ACRSL facility adjacent to the CEMRC in Carlsbad. An alternative is to construct and operate a new actinide chemistry laboratory on the WIPP site. The No Action Alternative is to continue experimental activities in actinide chemistry at existing laboratory facilities at LANL. The descriptions of the design, construction, and operation of the proposed ACRSL facility were obtained from the proposal submitted by the CEMRC (2000). -
Detection of Missing Low-Lying Atomic States in Actinium
Detection of missing low-lying atomic states in actinium Ke Zhang,1, 2, ∗ Dominik Studer,2 Felix Weber,2 Vadim M. Gadelshin,2, 3 Nina Kneip,2 Sebastian Raeder,1, 2 Dmitry Budker,1, 2, 4 Klaus Wendt,2 Tom Kieck,2, 1 Sergey G. Porsev,5, 6 Charles Cheung,5 Marianna S. Safronova,5, 7 and Mikhail G. Kozlov6, 8 1Helmholtz Institute Mainz, GSI Helmholtzzentrum f¨urSchwerionenforschung, 55099 Mainz, Germany 2Johannes Gutenberg-University Mainz, 55099 Mainz, Germany 3Institute of Physics and Technology, Ural Federal University, 620002 Yekaterinburg, Russia 4Department of Physics, University of California at Berkeley, California 94720-300, USA 5Department of Physics and Astronomy, University of Delaware, DE, 19716, USA 6Petersburg Nuclear Physics Institute of NRC \Kurchatov Institute", Gatchina 188300, Russia 7Joint Quantum Institute, NIST and the University of Maryland, College Park, MD, 20742, USA 8Petersburg Electrotechnical University \LETI", Prof. Popov Str. 5, 197376 St. Petersburg, Russia 2 2 o 2 2 o Two lowest-energy odd-parity atomic levels of actinium, 7s 7p P1=2, 7s 7p P3=2, were observed via two-step resonant laser-ionization spectroscopy and their respective energies were measured to be 7477:36(4) cm−1 and 12 276:59(2) cm−1. The lifetimes of these states were determined as 668(11) ns and 255(7) ns, respectively. In addition, these properties were calculated using a hybrid approach that combines configuration interaction and coupled-cluster methods in good agreement. The data are of relevance for understanding the complex atomic spectra of actinides and for developing efficient laser-cooling and ionization schemes for actinium, with possible applications for high-purity medical- isotope production and future fundamental physics experiments with this atom. -
Nuclear Engineering and Technology 49 (2017) 562E568
Nuclear Engineering and Technology 49 (2017) 562e568 Available online at ScienceDirect Nuclear Engineering and Technology journal homepage: www.elsevier.com/locate/net Original Article Analysis of Zirconium and Nickel Based Alloys and Zirconium Oxides by Relative and Internal Monostandard Neutron Activation Analysis Methods * Amol D. Shinde a, Raghunath Acharya b, , and Annareddy V.R. Reddy a a Analytical Chemistry Division, Mod Labs, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India b Radiochemistry Division, Radiological Laboratories, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India article info abstract Article history: Background: The chemical characterization of metallic alloys and oxides is conventionally Received 9 March 2016 carried out by wet chemical analytical methods and/or instrumental methods. Instru- Received in revised form mental neutron activation analysis (INAA) is capable of analyzing samples nondestruc- 1 August 2016 tively. As a part of a chemical quality control exercise, Zircaloys 2 and 4, nimonic alloy, and Accepted 19 September 2016 zirconium oxide samples were analyzed by two INAA methods. The samples of alloys and Available online 6 February 2017 oxides were also analyzed by inductively coupled plasma optical emission spectroscopy (ICP-OES) and direct current Arc OES methods, respectively, for quality assurance pur- Keywords: poses. The samples are important in various fields including nuclear technology. AES Methods: Samples were neutron irradiated using nuclear reactors, and the radioactive assay Chemical Quality Control was carried out using high-resolution gamma-ray spectrometry. Major to trace mass IM-NAA fractions were determined using both relative and internal monostandard (IM) NAA INAA methods as well as OES methods. -
Global Fissile Material Report 2015 Nuclear Weapon and Fissile Material Stockpiles and Production
Global Fissile Material Report 2015 Nuclear Weapon and Fissile Material Stockpiles and Production Eighth annual report of the International Panel on Fissile Materials Eighth annual report of the International Panel on Fissile Materials Global Fissile Material Report 2015 Nuclear Weapon and Fissile Material Stockpiles and Production 2015 International Panel on Fissile Materials This work is licensed under the Creative Commons Attribution-Noncommercial License To view a copy of this license, visit www.creativecommons.org/licenses/by-nc/3.0 On the cover: the map shows existing uranium enrichment and plutonium separation (reprocessing) facilities. Table of Contents About the IPFM 1 Summary 2 Nuclear Weapons 4 Highly Enriched Uranium 10 Military HEU 13 Civilian Use of HEU 17 Civilian Uranium Enrichment Plants 19 Separated Plutonium 23 Weapons Plutonium 25 Civilian Plutonium 29 Nuclear Weapons, Fissile Materials and Transparency 34 Appendix 1. Fissile Materials and Nuclear Weapons 40 Appendix 2. Uranium Enrichment Plants 48 Appendix 3. Reprocessing Plants 49 Appendix 4. Civilian Plutonium Stockpile Declarations 50 Endnotes 51 About the IPFM The International Panel on Fissile Materials (IPFM) was founded in January 2006. It is an independent group of arms-control and nonproliferation experts from seventeen countries, including both nuclear weapon and non-nuclear weapon states. The mission of the IPFM is to analyze the technical basis for practical and achievable policy initiatives to secure, consolidate, and reduce stockpiles of highly enriched urani- um and plutonium. These fissile materials are the key ingredients in nuclear weapons, and their control is critical to nuclear disarmament, halting the proliferation of nuclear weapons, and ensuring that terrorists do not acquire nuclear weapons. -
BERRIES Issue: 1 SAC Date: Nov 2020 Page: 1 of 22
Doc No: DLS-SACDISCo-BERRIES Issue: 1 SAC Date: Nov 2020 Page: 1 of 22 BERRIES (Bright Environment for x-ray Raman, Resonance Inelastic and Emission Spectroscopies) Prepared for Diamond SAC/DISCo November 2020 1 Doc No: DLS-SACDISCo-BERRIES Issue: 1 SAC Date: Nov 2020 Page: 2 of 22 1. Acknowledgements Working Group members: Dr Silvia Ramos, University of Kent (Champion) Prof. Andrea Russell, Southampton University (DUC representative) Dr Philip Ash, University of Leicester Dr Mike Baker, University of Manchester Dr Nathan Hollingsworth, Infineum UK Ltd. Dr Tim Hyde, Johnson Matthey Dr Bhoopesh Mishra, University of Leeds Dr Thomas Penfold, Newcastle University Prof. Sven Schroeder, University of Leeds Prof. Susannah Speller, University of Oxford Dr Gosia Swadzba-Kwasny, Queen’s University Belfast Prof. Robert Weatherup, University of Oxford Dr Sofia Diaz-Moreno, Diamond Light Source (Spectroscopy Science Group Leader) Dr Monica Amboage, Diamond Light Source (Diamond’s Lead) Dr Diego Gianolio, Diamond Light Source (Diamond’s Lead) Additional contributors: Dr Peter Wells (Southampton University), Dr Feng Ryan Wang (University College London), Dr Anna Kroner, Dr John Sutter, Martin Burt, Steve Millward (Diamond Light Source). UWG meetings: 2nd September 2020, 30th September 2020, 12th October 2020, 26th October 2020. Webinar: 14th October 2020 2 Doc No: DLS-SACDISCo-BERRIES Issue: 1 SAC Date: Nov 2020 Page: 3 of 22 2. Executive Summary This proposal sets out the case for developing internationally competitive photon-in/photon-out spectroscopy capabilities in the UK. The proposed beamline, BERRIES, will bring two new techniques to Diamond, pink-beam X-ray emission spectroscopy (pink-beam XES) and X-ray Raman scattering (XRS), whilst also enhancing the provision of high energy resolution fluorescence detection XAS (HERFD-XAS) and resonance XES (RXES). -
TRANSITION from OPERATION to DECOMMISSIONING of CIRUS RESEARCH REACTOR by Rakesh Ranjan, S
BARC/2018/E/005 BARC/2018/E/005 TRANSITION FROM OPERATION TO DECOMMISSIONING OF CIRUS RESEARCH REACTOR by Rakesh Ranjan, S. Bhattacharya, C.G . Karhadkar, Prasit Mandal, M.K. Ojha Reactor Operations Division 2018 BARC/2018/E/005 GOVERNMENT OF INDIA DEPARTMENT OF ATOMIC ENERGY BARC/2018/E/005 TRANSITION FROM OPERATION TO DECOMMISSIONING OF CIRUS RESEARCH REACTOR by Rakesh Ranjan*, S. Bhattacharya, C.G . Karhadkar, Prasit Mandal, M.K. Ojha [email protected]* Reactor Operations Division Reactor Group BHABHA ATOMIC RESEARCH CENTRE MUMBAI, INDIA 2018 BARC/2018/E/005 BIBLIOGRAPHIC DESCRIPTION SHEET FOR TECHNICAL REPORT (as per IS : 9400 - 1980) 01 Security classification : Unclassified 02 Distribution : External 03 Report status : New 04 Series : BARC External 05 Report type : Technical Report 06 Report No. : BARC/2018/E/005 07 Part No. or Volume No. : 08 Contract No. : 10 Title and subtitle : Transition from operation to decommissioning of Cirus research reactor 11 Collation : 82 p., 39 figs., 9 tabs. 13 Project No. : 20 Personal author(s) : Rakesh Ranjan; S. Bhattacharya, C.G. Karhadkar; Prasit Mandal; M.K. Ojha 21 Affiliation of author(s) : Reactor Operations Division, Bhabha Atomic Research Centre, Mumbai 22 Corporate author(s): Bhabha Atomic Research Centre, Mumbai - 400 085 23 Originating unit : Reactor Operations Division, Bhabha Atomic Research Centre, Mumbai 24 Sponsor(s) Name : Department of Atomic Energy Type : Government Contd... BARC/2018/E/005 30 Date of submission : April 2018 31 Publication/Issue date : April 2018 40 Publisher/Distributor : Head, Scientific Information Resource Division, Bhabha Atomic Research Centre, Mumbai 42 Form of distribution : Hard copy 50 Language of text : English 51 Language of summary : English 52 No. -
Fiscal Year 2016 Award Abstracts
DOE Office of Science Early Career Research Program Awardee Abstracts Fiscal Year 2016 Laser Driven X‐ray Sources for High Energy Density Science Experiments Dr. Félicie Albert, Research Scientist Hohlraum Physics and Optical Diagnostics Group High Energy Density Science and Technology Division National Ignition Facility and Photon Science Directorate Lawrence Livermore National Laboratory Livermore, CA 94551 Understanding the relationships between temperature, pressure, and density in extreme environments is one of the grand challenges of high energy density (HED) plasma science. Lasers and x‐ ray free electron laser (XFEL) facilities are now capable of driving matter to extreme states of temperature and pressure. However, these HED plasmas are extremely difficult to probe because most of the time they are in a non‐equilibrium state and are transient in nature. Hence, there is a critical need to configure and test new diagnostic tools to measure the properties and dynamics of HED plasmas. This project brings one of the most promising applications of laser‐based plasma accelerators (betatron x‐ray radiation) to probe HED plasmas with unprecedented sub‐picosecond resolution. Our research will generate new data on sub‐picosecond dynamics of electron‐ion equilibration in warm dense matter, laser‐driven shocks, and opacity in HED plasmas that cannot be measured by other existing methods. Our integrated experimental approach, combined with a host of theoretical models and tools, will allow us to probe radiation‐matter interactions under extreme conditions to accelerate breakthroughs in frontier plasma science. This research was selected for funding by the Office of Fusion Energy Sciences. 1 DOE Office of Science Early Career Research Program Awardee Abstracts Fiscal Year 2016 Ultrafast Dynamics of Molecules on Surfaces Studied with Time‐Resolved XUV Photoelectron Spectroscopy Dr.