DOCSLIB.ORG

Study of Macromolecule-Mineral Interactions on Nuclear Related Materials

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Study of Macromolecule-Mineral Interactions on Nuclear Related Materials Study of macromolecule-mineral interactions on nuclear related materials by Lygia Eleftheriou Submitted in partial fulfillment of the requirements for the degree of Doctor of Philosophy Supervised by: Prof John Harding Dr Maria Romero-González The University of Sheffield Faculty of Engineering Department of Materials Science and Engineering September 2016 Declaration The work described within this thesis has been completed under the supervision of Prof J. Harding and Dr M. Romero-González at the University of Sheffield between September 2012 and September 2016. This thesis along with the work described here has been completed by the author with some exceptions indicated clearly at the relevant chapters. These include: (1) the construction of ceria models for the computational work that was completed by Dr Colin Freeman and Dr Shaun Hall (described in chapter 5), (2) the purification of peptidoglycan completed by Dr Stephane Mesnage (described in chapter 4) and (3) the electron microscopy analysis completed by Dr Mohamed Merroun (described in chapter 2). Lygia Eleftheriou September 2016 Acknowledgements I would like to express my sincere gratitude to my supervisors Dr Maria Romero González and Prof John Harding for all their support during the past four years. This work would not have been possible without their endless encouragement, guidance and advice. I would also like to thank Dr Colin Freeman, Dr Shaun Hall and Riccardo Innocenti Malini for all the hours they spent trying to make things work and all their help with the computational part of this project. In addition, I would like to thank Dr Simon Thorpe, Dr Stephane Mesnage and Mr Robert Hanson for their help with the analytical methods of this project. Special thanks should go to Debbie Hill, Emma Wharfe and Gordon Brown for being my first contact for basically everything, from outreach activities to student support. Lastly, I would like to thank my family and friends. My parents were the ones to support me the most during this journey. I could never thank them enough. My dear friends, Gifty Tetteh and Joe Hufton who in one way or another shared their support and of course my partner-in- crime, Panagiotis Koulouris who has been next to me during the endless nights of analysing, correcting, writing, re-writing and so on. Thank you! The research was sponsored financially by the EPSRC Doctoral Training Centre (DTC) in Nuclear Fission Research Science and Technology and the EPSRC consortium 'Hard-soft matter interfaces: from understanding to engineering' (EP/I001514/1). Abstract Microbes have been identified close to contaminated sites such as nuclear-waste repositories indicating their ability to interact with radionuclides. One of the main mechanisms bacteria use involves the reduction of highly mobile radionuclides to less mobile minerals, often in the form of oxides. The precipitated minerals are found located at the cell wall or close to the external components of the bacterial cell suggesting a possible interaction of cell wall components or external components of the tested bacteria with the precipitated particles. Tests on ceria, urania, thoria and europium oxide confirmed that several biomolecules are responsible for the observed localisation. The first experiments used lipopolysaccharides (LPS), found at the outer site of Gram negative bacterial cells and resulted in successful sorption of LPS on all four minerals. The Purpald assay was used to quantify LPS before and after the interaction and confirmed the attachment of the biopolymers to the oxides with ΔG values in the range of physisorption (-3 to -25 kJ/mol) for all systems. ATR-FTIR, zeta potential analysis and electron microscopy also confirmed the attachment of the biomolecules on the minerals. Mycolic acids and peptidoglycans, components of Gram positive bacteria, were also assessed for their ability to interact with ceria and europium oxide. Mycolic acids showed successful sorption profiles with ΔG values in the physisorption range (-10 to -17 kJ/mol) for all systems, highly dependent on the experimental conditions. In addition, Molecular Dynamics simulations were used to examine the interaction of mycolic acid with ceria under natural conditions (pH7) in the presence of Na+ and the calculated binding energy (-11.598 kJ/mol) agreed well with the experimental results for the corresponding system (-16.485 kJ/mol). Additionally, preliminary tests on peptidoglycan interactions resulted in successful sorption of the biomolecule on both ceria and europium oxide with ΔG values in the physisorption range (-8 to -10 kJ/mol). ATR- FTIR and zeta potential analysis confirmed the attachment of mycolic acid and peptidoglycan on the minerals tested. These results suggest that the observed localisation of mineral within the bacterial cell walls are related to lipopolysaccharide and peptidoglycan-mediated sorption and have potential uses in treatment of nuclear waste and biomining processes. Contents Page Chapter 1 ........................................................................................................................................................ 15 Introduction ................................................................................................................................................... 15 Background ................................................................................................................................................ 16 Objectives ................................................................................................................................................... 17 Literature review ....................................................................................................................................... 18 1.1 Nuclear Materials: Existence and Usage.................................................................................... 18 1.2 The issue .................................................................................................................................... 19 1.3 Bacterial interactions with nuclear-related materials ................................................................. 19 1.3.1 Bacterial cell structure ............................................................................................................... 22 1.3.1.1 Gram negative and Gram positive bacteria ........................................................................ 22 1.3.1.2 The Mycolata family .......................................................................................................... 23 1.4. Interactions of cell wall bio-components with minerals .................................................................. 24 1.4.1 Lipopolysaccharides .................................................................................................................. 24 1.4.2 Peptidoglycans ........................................................................................................................... 25 1.4.3 Mycolic acids ................................................................................................................................. 25 1.5. Importance and applications of interactions between bacterial components and nuclear-related minerals ................................................................................................................................................... 26 1.6 Experimental techniques to evaluate macromolecule-mineral interactions ...................................... 28 1.6.1 Spectrophotometric Techniques ................................................................................................ 28 1.6.2 Spectroscopic techniques-FTIR ..................................................................................................... 30 1.6.3 Computational Methods............................................................................................................. 31 1.6.3.1 Molecular Dynamics .......................................................................................................... 33 Chapter 2 ........................................................................................................................................................ 45 Lipopolysaccharide Interactions with Nuclear Related Minerals ............................................................. 45 2.1 Introduction ......................................................................................................................................... 46 2.1.1 Functions of LPS ............................................................................................................................ 48 2.1.1.1 Interactions of LPS with surfaces ........................................................................................... 49 2.1.2 Objectives ...................................................................................................................................... 51 2.2 Materials and Methods ....................................................................................................................... 52 2.2.1 Chemicals ....................................................................................................................................... 52 2.2.2 Macromolecules ............................................................................................................................. 52 2.2.2.1 Molecular Weight Determination of LPS ..............................................................................
Load more

Recommended publications
  • Development of an On-Line Fuel Failure Monitoring System For
    DEVELOPMENT OF AN ON-LINE FUEL FAILURE MONITORING SYSTEM FOR CANDU REACTORS DEVELOPPEMENT D'UN SYSTEME DE SURVEILLANCE EN LIGNE POUR DES RUPTURES DE GAINES DES REACTEURS CANDU A Thesis Submitted to the Division of Graduate Studies of the Royal Military College of Canada by Stephen Jason Livingstone, BSc, MSc Sub-Lieutenant In Partial Fulfillment of the Requirements for the Degree of Doctor of Philosophy March 2012 ©This thesis may be used within the Department of National Defence but copyright for open publication remains the property of the author. Library and Archives Bibliotheque et Canada Archives Canada Published Heritage Direction du Branch Patrimoine de I'edition 395 Wellington Street 395, rue Wellington Ottawa ON K1A0N4 Ottawa ON K1A 0N4 Canada Canada Your file Votre reference ISBN: 978-0-494-83407-7 Our file Notre reference ISBN: 978-0-494-83407-7 NOTICE: AVIS: The author has granted a non­ L'auteur a accorde une licence non exclusive exclusive license allowing Library and permettant a la Bibliotheque et Archives Archives Canada to reproduce, Canada de reproduire, publier, archiver, publish, archive, preserve, conserve, sauvegarder, conserver, transmettre au public communicate to the public by par telecommunication ou par Plnternet, preter, telecommunication or on the Internet, distribuer et vendre des theses partout dans le loan, distrbute and sell theses monde, a des fins commerciales ou autres, sur worldwide, for commercial or non­ support microforme, papier, electronique et/ou commercial purposes, in microform, autres formats. paper, electronic and/or any other formats. The author retains copyright L'auteur conserve la propriete du droit d'auteur ownership and moral rights in this et des droits moraux qui protege cette these.
    [Show full text]
  • 小型飛翔体／海外 ［Format 2］ Technical Catalog Category
    小型飛翔体／海外 ［Format 2］ Technical Catalog Category Airborne contamination sensor Title Depth Evaluation of Entrained Products (DEEP) Proposed by Create Technologies Ltd & Costain Group PLC １．DEEP is a sensor analysis software for analysing contamination. DEEP can distinguish between surface contamination and internal / absorbed contamination. The software measures contamination depth by analysing distortions in the gamma spectrum. The method can be applied to data gathered using any spectrometer. Because DEEP provides a means of discriminating surface contamination from other radiation sources, DEEP can be used to provide an estimate of surface contamination without physical sampling. DEEP is a real-time method which enables the user to generate a large number of rapid contamination assessments- this data is complementary to physical samples, providing a sound basis for extrapolation from point samples. It also helps identify anomalies enabling targeted sampling startegies. DEEP is compatible with small airborne spectrometer/ processor combinations, such as that proposed by the ARM-U project – please refer to the ARM-U proposal for more details of the air vehicle. Figure 1: DEEP system core components are small, light, low power and can be integrated via USB, serial or Ethernet interfaces. 小型飛翔体／海外 Figure 2: DEEP prototype software ２．Past experience (plants in Japan, overseas plant, applications in other industries, etc) Create technologies is a specialist R&D firm with a focus on imaging and sensing in the nuclear industry. Createc has developed and delivered several novel nuclear technologies, including the N-Visage gamma camera system. Costainis a leading UK construction and civil engineering firm with almost 150 years of history.
    [Show full text]
  • Physics 111 Fall 2007 Radioactive Decay Problems Solutions
    Physics 111 Fall 2007 Radioactive Decay Problems Solutions 3 1. The 1 H isotope of hydrogen, which is called tritium (because it contains three nucleons), has a half-life of 12.33 yr. It can be used to measure the age of objects up to about 100 yr. It is produced in the upper atmosphere by cosmic rays and brought to Earth by rain. As an application, determine approximately the age of a bottle of wine 3 1 whose 1 H radiation is about 10 that present in new wine. Because the tritium in water is being replenished, we assume that the amount is constant until the wine is made, and then it decays. We find the number of half-lives from N n = 1 ; N ()2 0 n 0.10 = 1 , or n log 2 = log 10 , which gives n = 3.32. ()2 () Thus the time is t = nT = 3.32 12.33 yr = 41 yr. 1 ()() 2 2. Strontium-90 is produced as a nuclear fission product of uranium in both reactors and atomic bombs. Look at its location in the periodic table to see what other elements it might be similar to chemically, and tell why you think it might be dangerous to ingest. It has too many neutrons, and it decays with a half-life of about 29 yr. How 90 long will we have to wait for the amount of 38 Sr on the Earth’s surface to reach 1% of its current level, assuming no new material is scattered about? Write down the decay reaction, including the daughter nucleus.
    [Show full text]
  • Perspective the Radioactivity of Atmospheric Krypton in 1949–1950
    Proc. Natl. Acad. Sci. USA Vol. 94, pp. 7807–7810, July 1997 Perspective The radioactivity of atmospheric krypton in 1949–1950 Anthony Turkevich*, Lester Winsberg†, Howard Flotow‡, and Richard M. Adams§ Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439 Contributed by Anthony Turkevich, April 10, 1997 ABSTRACT The chemical element krypton, whose prin- Libby (in 1948; unpublished work) gave indications that these cipal source is the atmosphere, had a long-lived radioactive predictions were correct. The present report describes the content, in the mid-1940s, of less than 5 dpm per liter of technique that was used soon afterward to establish more krypton. In the late 1940s, this content had risen to values in precisely that atmospheric krypton in the late 1940s was much the range of 100 dpm per liter. It is now some hundred times more radioactive than it had been, and gives the results of some higher than the late 1940 values. This radioactivity is the early measurements of krypton samples isolated from the result of the dissolving of nuclear fuel for military and civilian atmosphere at that time.** purposes, and the release thereby of the fission product krypton-85 (half-life 5 10.71 years, fission yield 5 0.2%). The Measurement Technique present largest emitter of krypton-85 is the French reprocess- ing plant at Cap-de-la-Hague. The measurement technique that was used was influenced by those simultaneously being developed by Libby and Anderson It is generally known that the chemical element krypton, (9) to measure the radiocarbon content of samples of arche- isolated from the atmosphere in 1996, is radioactive.
    [Show full text]
  • RCC-Mrx Chairwoman CEA - Senior Expert in Design Codes and Standards for Mechanical Components
    Shaping the rules for a sustainable nuclear technology How to introduce new materials in design codes Cécile PÉTESCH RCC-MRx chairwoman CEA - Senior Expert in design codes and standards for mechanical components SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 1 Shaping the rules for a sustainable nuclear technology Design codes vs new material Why? Interest to connect R&D to standardisation What? Example of RCC-MRx code How? Difficulties to introduce a new material Conclusion SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 2 Shaping the rules for a sustainable nuclear technology Design codes vs new material Why? Interest to connect R&D to standardisation What? Example of RCC-MRx code How? Difficulties to introduce a new material Conclusion SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 3 Why? Codes and standards Modification request Material file Nuclear Industry New Material SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 4 Why? Codes and standards DMRx Material file REGULATOR New Material SNETP FORUM 2021 Towards innovative R&D in civil nuclear fission AFCEN is ISO 9001:2015 certified © 2021 www.afcen.com | 5 Why? For innovative reactors, standardization is one way to reach a highest technology readiness level, giving a frame and a direction
    [Show full text]
  • Accumulation and Mobility of Radionuclides in the Sellafield Near-Shore
    Accumulation and Mobility of Radionuclides in the Sellafield Near-Shore A thesis submitted to the University of Manchester for the degree of Master of Science by Research in the Faculty of Engineering and Physical Sciences 2013 Daisy Ray School of Chemistry Contents Contents 2 List of Figures 5 Abstract 7 Declaration 8 Copyright 8 Chapter 1 Introduction 10 1.1. Overview 11 1.2. Thesis Structure 11 1.3. Nuclear Power 12 1.3.1 Early Development and Contemporary Demand 12 1.3.2. The UK Nuclear Legacy 13 1.4. The Nuclear Fuel Cycle 14 1.4.1. Mining and Milling of Uranium Ore 15 1.4.2. Purification and Fuel Fabrication 15 1.4.3. Reactor Operation 16 1.4.4. Spent Fuel Reprocessing 17 1.5. Sellafield 19 1.5.1. Operational History of Sellafield 19 1.6. Radionuclides in the Environment 20 1.6.1. Authorised Sellafield Discharges 21 2 1.7. The Chemistry of Select Actinides and Fission Products in Sellafield Effluents 23 1.7.1. Plutonium 23 1.7.2. Americium 26 1.7.3. Caesium 27 1.8. Biogeochemistry of the Natural Environment 27 1.8.1. Sorption 28 1.8.2. Incorporation/Precipitation 29 1.8.3. Redox Reactions 29 1.8.4. Bioturbation 30 1.8.5. Microbial Activity 31 1.9. Mechanism of Radionuclide Transportation 33 1.10. Project Aims 35 Chapter 2 Materials and Methods 37 2.1. Sample Collection 38 2.2. Major and Minor elemental analysis 39 2.3. Americium and Caesium Detection 40 2.3.1.
    [Show full text]
  • Magnetic Field Generation in Planets and Satellites by Natural Nuclear Fission Reactors
    Magnetic Field Generation in Planets and Satellites by Natural Nuclear Fission Reactors by J. Marvin Herndon Transdyne Corporation San Diego, CA 92131 USA 27 July 2007 Communications: [email protected] http://UnderstandEarth.com Keywords: Planetary Magnetic Field, Geomagnetism, Geomagnetic Field, Georeactor Abstract: One of the most fundamental problems in physics has been to understand the nature of the mechanism that generates the geomagnetic field and the magnetic fields of other planets and satellites. For decades, the dynamo mechanism, thought to be responsible for generating the geomagnetic field and other planetary magnetic fields, has been ascribed to convection in each planet’s iron-alloy core. Recently, I described the problems inherent in Earth-core convection and proposed instead that the geomagnetic field is produced by convection in the electrically conductive, fluid, fission-product sub-shell of a natural nuclear fission reactor at the center of the Earth, called the georeactor. Here I set forth in detail the commonality in the Solar System of the matter like that of the inside of the Earth, which is my basis for generalizing the concept of planetary magnetic field generation by natural planetocentric nuclear fission reactors. Introduction Currently active internally generated magnetic fields have been detected in six planets (Mercury, Earth, Jupiter, Saturn, Uranus, and Neptune) and in one satellite (Jupiter’s moon Ganymede). Magnetized surface areas of Mars and the Moon indicate the former existence of internally generated magnetic fields in those bodies. The purpose of this communication is to suggest that those magnetic fields arise from the same georeactor-type mechanism which I have suggested generates and powers the Earth’s magnetic field [1].
    [Show full text]
  • Average Beta and Gamma Decay Energies of the Fission Products
    AN ABSTRACT OF THE THESIS OE Chi Hung Wu for the degree of Doctor of Philosophy in Nuclear Engineering presented onAugust 10, 1978 Title: Avera e Beta and Gamma DecaEner ies of the Fission Products Abstract approved: Redacted for privacy Bernal& I. Spinrad One method of predicting the decay-heat is the "SummationMethod" in which the power produced by decay of each fission product at time t after shut-down is calculated. The reactor shut-down power produced at time t is then obtained by summing over all of the fissionproducts. An accurate determination of the average beta and gamma decayenergies is essential for the success of this method. Out of approximately 850 fission products, there are only about 150 whose beta and gamma decay energies have been measured. The rest were predicted by a fitting formula in whichthe ratio of decay energy to beta-decay Q value is taken as a linear sumof terms in mass number, charge number, and nuclear pairing energy; the coefficients weredeter- mined by a least-squares fit to known data. Instead of fitting, the average beta and gamma decay energies can be calculated theoretically. Nuclear models, such as the shell model and the collective model, can predict the first fewlow-lying excited states quite well on the average. On the other hand, the statistical model can be used for higher excited states, which we can approxi- mate by assuming that the states form a continuum. The probability of beta decay can be taken as proportional to E5p, where E is the beta end-point energy and p is the angular- momentum-dependent level density.
    [Show full text]
  • Calculations Related to Nuclear Fission-Product Yields
    XA9744983 _ International Atomic Energy Agency INDCCCCP1-4Q4 Distr.: L IN DC INTERNATIONAL NUCLEAR DATA COMMITTEE CALCULATIONS RELATED TO NUCLEAR FISSION-PRODUCT YIELDS Three papers by E.S. Bogomolova, A.F. Grashin, A.D. Efimenko, I.B. Lukasevich Moscow Engineering Physics Institute, Moscow Translated by the IAEA August 1997 IAEA NUCLEAR DATA SECTION, WAGRAMERSTRASSE 5. A 1400 VIENNA Reproduced by the IAEA in Austria August 1997 INDC1CCPV404 Distr.: L CALCULATIONS RELATED TO NUCLEAR FISSION-PRODUCT YIELDS Three papers by E.S. Bogomolova, A.F. Grashin, A.D. Efimenko, I.B. Lukasevich Moscow Engineering Physics Institute, Moscow Original articles in Russian published in Jadernye Konstanty (Nuclear Constants) Volumes 1-2, 1995 Translated by the IAEA August 1997 Contents The ASIND-MEPhI Library of Independent Actinide ........................................................ 7 Fission Product Yields (English translation from Yad. Konst. 1-2, 1995, p. 89) Calculation of Independent Fission Product Yields by ...................................................... 25 the Thermodynamic Method (English translation from Yad. Konst. 1-2, 1995, p. 99) Long-Lived Fission Product Yields and the Nuclear .........................................................51 Transmutation Problem (English translation from Yad. Konst. 1-2, 1995, p. 117) XA9744984 - 7 - 96-11496 (N) Translated from Russian UDC 539.173 THE ASIND-MEPhI LIBRARY OF INDEPENDENT ACTINIDE FISSION PRODUCT YIELDS E.S. Bogomolova, A.F. Grashin, A.D. Efimenko, LB. Lukasevich Moscow Engineering Physics Institute, Moscow ABSTRACT THE ASIND-MEPhI LIBRARY OF INDEPENDENT ACTINIDE FISSION PRODUCT YIELDS. This database of independent fission product yields has been set up at the Moscow Engineering Physics Institute on the basis of theoretical calculations within the framework of the super-nonequilibrium thermodynamic model.
    [Show full text]
  • FY 2014 Volume 5
    DOE/CF-0088 Volume 5 Department of Energy FY 2014 Congressional Budget Request Environmental Management April 2013 Office of Chief Financial Officer Vo l u me 5 DOE/CF-0088 Volume 5 Department of Energy FY 2014 Congressional Budget Request Environmental Management April 2013 Office of Chief Financial Officer Vo l u me 5 Printed with soy ink on recycled paper Volume 5 Table of Contents Section Appropriation Account Summary .......................................................................................................................................... AP Appropriation Language .................................................................................................................................................... EM-1 Overview ............................................................................................................................................................................ EM-3 Carlsbad ........................................................................................................................................................................... EM-49 Idaho ................................................................................................................................................................................ EM-59 Oak Ridge ......................................................................................................................................................................... EM-73 Paducah ..........................................................................................................................................................................
    [Show full text]
  • Active Interrogation Using Photofission Technique for Nuclear Materials Control and Accountability
    Project No. 11-3035 Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability Fuel Cycle Research and Development Maori Yang Oregon State University Dan Vega, Federal ROC Mike Miller, Technical ROC FINAL REPORT Project Title: Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability Covering Period: November, 2011 - November, 2015 Contract Number: 120873 Date of Report: March 11, 2016 Principal Investigator: Haori Yang, [email protected] Co-PI: Daren Norman, [email protected] Dante Nakazawa, [email protected] Submitted by: Haori Yang, Ph D. School of Nuclear Science and Engineering Oregon State University Prepared by: Xianfei Wen, Haori Yang Abstract Innovative systems with increased sensitivity and resolution are in great demand to detect diversion and to prevent misuse in support of nuclear materials management for the U.S. fuel cycle. Nuclear fission is the most important multiplicative process involved in non-destructive active interrogation. This process produces the most easily recognizable signature for nuclear materials. In addition to thermal or high-energy neutrons, high-energy gamma rays can also excite a nucleus and cause fission through a process known as photofission. Electron linear accelerators (linac) are widely used as the interrogating photon sources for inspection methods involving photofission technique. After photofission reactions, prompt signals are much stronger than the delayed signals, but it is difficult to quantify them in practical measurements. Delayed signals are easily distinguishable from the interrogating radiation. linac-based, advanced inspection techniques utilizing the delayed signals after photofission have been extensively studied for homeland security applications. Previous research also showed that a unique delayed gamma ray energy spectrum exists for each fissionable isotope.
    [Show full text]
  • WM2010 Conference, March 7-11, 2010, Phoenix, AZ Some Recent
    WM2010 Conference, March 7-11, 2010, Phoenix, AZ Some Recent Technology Developments From The UK’s National Nuclear Laboratory To Enable Hazard Characterisation For Nuclear Decommissioning Applications - 10317 C.J. Holmes*, E.B.Farfan**, T.Q. Foley**, M. Oldham+, T. York++, P. Green++, P. Jackson+++, S.J. Stanley*, * National Nuclear Laboratory, Risley, Warrington, United Kingdom ** Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 + Duke University Medical Center, Durham, NC 27710 ++School of Electrical and Electronic Engineering, University of Manchester, Manchester, United Kingdom +++Tracerco Ltd, Billingham, Cleveland, United Kingdom ABSTRACT Under its programme of self investment Internal Research and Development (IR&D), the UK’s National Nuclear Laboratory (NNL) is addressing the requirement for development in technology to enable hazard characterisation for nuclear decommissioning applications. Three such examples are described here: RadBall developed by the NNL (patent pending) is a deployable baseball-sized radiation mapping device which can, from a single location, locate and quantify radiation hazards. RadBall offers a means to collect information regarding the magnitude and distribution of radiation in a given cell, glovebox or room to support the development of a safe, cost effective decontamination strategy. RadBall requires no electrical supplies and is relatively small, making it easy to be deployed and used to map radiation hazards in hard to reach areas. Recent work conducted in partnership with the Savannah River National Nuclear Laboratory (SRNL) is presented. HiRAD (patent pending) has been developed by the NNL in partnership with Tracerco Ltd (UK). HiRAD is a real-time, remotely deployed, radiation detection device designed to operate in elevated levels of radiation (i.e.
    [Show full text]