DOCSLIB.ORG

WO 2014/186898 Al 27 November 2014 (27.11.2014) P O P C T

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
WO 2014/186898 Al 27 November 2014 (27.11.2014) P O P C T (12) INTERNATIONAL APPLICATION PUBLISHED UNDER THE PATENT COOPERATION TREATY (PCT) (19) World Intellectual Property Organization International Bureau (10) International Publication Number (43) International Publication Date WO 2014/186898 Al 27 November 2014 (27.11.2014) P O P C T (51) International Patent Classification: (74) Agents: POLONENKO, Daniel et al; Gowling Lafleur G21G 1/12 (2006.01) C01G 39/00 (2006.01) Henderson LLP, Suite 2300, 550 Burrard Street, Van G21K 5/08 (2006.01) H05H 9/00 (2006.01) couver, British Columbia V6C 2B5 (CA). (21) International Application Number: (81) Designated States (unless otherwise indicated, for every PCT/CA20 14/050479 kind of national protection available): AE, AG, AL, AM, AO, AT, AU, AZ, BA, BB, BG, BH, BN, BR, BW, BY, (22) International Filing Date: BZ, CA, CH, CL, CN, CO, CR, CU, CZ, DE, DK, DM, 23 May 2014 (23.05.2014) DO, DZ, EC, EE, EG, ES, FI, GB, GD, GE, GH, GM, GT, (25) Filing Language: English HN, HR, HU, ID, IL, IN, IR, IS, JP, KE, KG, KN, KP, KR, KZ, LA, LC, LK, LR, LS, LT, LU, LY, MA, MD, ME, (26) Publication Language: English MG, MK, MN, MW, MX, MY, MZ, NA, NG, NI, NO, NZ, (30) Priority Data: OM, PA, PE, PG, PH, PL, PT, QA, RO, RS, RU, RW, SA, 2816453 23 May 2013 (23.05.2013) CA SC, SD, SE, SG, SK, SL, SM, ST, SV, SY, TH, TJ, TM, TN, TR, TT, TZ, UA, UG, US, UZ, VC, VN, ZA, ZM, (71) Applicant: CANADIAN LIGHT SOURCE INC. ZW. [CA/CA]; 44 Innovation Boulevard, Saskatoon, Saskat chewan S7N 2V3 (CA). (84) Designated States (unless otherwise indicated, for every kind of regional protection available): ARIPO (BW, GH, (72) Inventors: DIAMOND, William; 7 Sheridan Court, (PO GM, KE, LR, LS, MW, MZ, NA, RW, SD, SL, SZ, TZ, BOX 1874), Deep River, Ontario K0J 1P0 (CA). UG, ZM, ZW), Eurasian (AM, AZ, BY, KG, KZ, RU, TJ, NAGARKAL, Vinay; 415-235 Herold Terrace, Saska TM), European (AL, AT, BE, BG, CH, CY, CZ, DE, DK, toon, Saskatchewan S7V 1J2 (CA). DE JONG, Mark; 5 18 EE, ES, FI, FR, GB, GR, HR, HU, IE, IS, IT, LT, LU, LV, Steiger Way, Saskatoon, Saskatchewan S7N 4K2 (CA). MC, MK, MT, NL, NO, PL, PT, RO, RS, SE, SI, SK, SM, REGIER, Christopher; 643 Frobisher Terrace, Saska TR), OAPI (BF, BJ, CF, CG, CI, CM, GA, GN, GQ, GW, toon, Saskatchewan S7K 4Z1 (CA). LIN, Linda; 562 KM, ML, MR, NE, SN, TD, TG). Maguire Lane, Saskatoon, Saskatchewan S7W 1A4 (CA). ULLRICH, Douglas; 413 Rossmo Rd., Saskatoon, Saskat Published: chewan S7N 2Y4 (CA). — with international search report (Art. 21(3)) (54) Title: PRODUCTION OF MOLYBDENUM-99 USING ELECTRON BEAMS Fig. 2 00 00 00 (57) Abstract: An apparatus for producing "Mo from a plurality of 1 Mo targets through a photo-nuclear reaction on the 1 Mo tar gets. The apparatus comprises (i) an electron linear accelerator component; (ii) an energy converter component capable of receiving the electron beam and producing therefrom a shower of bremsstrahlung photons; (iii) a target irradiation component for receiving the o shower of bremsstrahlung photons for irradiation of a target holder mounted and positioned therein. The target holder houses a plur ality of 1 Mo target discs. The apparatus additionally comprises (iv) a target holder transfer and recovery component for receiving, manipulating and conveying the target holder by remote control; (v) a first cooling system sealingly engaged with the energy con - o verter component for circulation of a coolant fluid therethrough; and (vi) a second cooling system sealingly engaged with the target irradiation component for circulation of a coolant fluid therethrough. TITLE: PRODUCTION OF MOLYBDENUM-99 USING ELECTRON BEAMS TECHNICAL FIELD The present disclosure pertains to processes, systems, and apparatus, for production of molybdenum-99. More particularly, the present disclosure pertains to production of molybdenum-99 from molybdenum- 100 targets using high-power electron linear accelerators. BACKGROUND Technetium-99m, referred to hereinafter as 99mTc, is one of the most widely used radioactive tracers in nuclear medicine diagnostic procedures. 99mTc is used routinely for detection of various forms of cancer, for cardiac stress tests, for assessing the densities of bones, for imaging selected organs, and other diagnostic testing. 99mTc emits readily detectable 140 keV gamma rays and has a half-life of only about six hours, thereby limiting patients' exposure to radioactivity. Because of its very short half-life, medical centres equipped with nuclear medical facilities derive 99mTc from the decay of its parent isotope molybdenum-99, referred to hereinafter as Mo, using 99mTc generators. Mo has a relatively long half life of 66 hours which enables its world-wide transport to medical centres from nuclear reactor facilities wherein large-scale production of Mo is derived from the fission of highly enriched 5Uranium. The problem with nuclear production of Mo is that its world-wide supply originates from five nuclear reactors that were built in the 1960s, and which are close to the end of their lifetimes. Almost two-thirds of the world's supply of Mo currently comes from two reactors: (i) the National Research Universal Reactor at the Chalk River Laboratories in Ontario, Canada, and (ii) the Petten nuclear reactor in the Netherlands. In the past few years, there have been major shortages of Mo as a consequence of planned or unplanned shutdowns at both of the major production reactors. Consequently, serious shortages occurred at the medical facilities within several weeks of the reactor shutdowns, causing significant reductions in the provision of medical diagnostic testing and also, placing great production demands on the remaining nuclear reactors. Although both facilities are now active again, there is much global uncertainty regarding a reliable long-term supply of Mo. SUMMARY The exemplary embodiments of the present disclosure pertain to apparatus, systems, and processes for the production of molybdenum-99 ( Mo) from molybdenum- 100 (1 Mo) by high-energy electron irradiation with linear accelerators. Some exemplary embodiments relate to systems for working the processes of present disclosure. Some exemplary embodiments relate to apparatus comprising the systems of the present disclosure. DESCRIPTION OF THE DRAWINGS The present disclosure will be described in conjunction with reference to the following drawings in which: Fig. 1 is a perspective illustration of an exemplary system of the present disclosure, shown with protective shielding in place; Fig. 2 is a perspective view of the exemplary system from Fig. 1, shown with the protective shielding removed; Fig. 3 is a side view of the exemplary system from Fig. 2, shown with protective shielding removed from the linear accelerator components of the system; Fig. 4 is a top view of the exemplary system shown in Fig. 3; Fig. 5 is an end view of the from Fig. 3, shown from the end with the linear accelerator components; Fig. 6(A) is a perspective view showing the target assembly component of the exemplary system from Fig. 2 partially unclad with the protective shielding component, while 6(B) is a perspective view showing the target assembly component unclad; Fig. 7 is a side view of the target drive assembly (perpendicular to the electron beam generated by the linear accelerator); Fig. 8 is a front view of the target drive assembly showing the inlet for the bremsstrahlung photon beam generated from the linac electron beam; Fig. 9 is a cross-sectional front view of the target drive assembly shown in Fig. 8; Fig. 10 is a cross-sectional top view of the target drive assembly shown in Fig. 8 at the junction of the cooling tower component and the housing for the beamline; Fig. 1 1 is a cross-sectional top view of the target drive assembly shown in Fig. 8 showing the target holder mounted in the beamline; Fig. 12 is schematic illustration of the conversion of a high-power electron beam into a bremsstrahlung photon shower for irradiation of a plurality of 1 Mo targets; Fig. 13 is close-up cross-sectional front view from Fig. 9 showing the mounted target holder; Fig. 14 is a close-up cross-sectional top view from Fig. 11 showing the mounted target holder; Fig. 15(A) is a perspective view of an exemplary target holder, while 15(B) is a cross- sectional side view of the target holder; Fig. 16(A) is a perspective view from the top of an exemplary cooling tube component, while 16(B) is a perspective view from the bottom of the cooling tube component, and 16(C) is a cross-sectional side view of the cooling tube component; Figs. 17(A) and 17(B) show another embodiment of a cooling tube component being installed into a target assembly component from Fig. 9; Figs. 18(A) and 18(B) show the cooling tube component from Fig. 17 being clamped into place within the target assembly component Fig. 19 is a perspective view of an exemplary remote-controlled molybdenum handling apparatus mounted onto the protective shield cladding of the target assembly station component of the exemplary system shown in Fig. 1; Fig. 20 is a perspective view of an exemplary frame support base for the exemplary remote-controlled molybdenum handling apparatus shown in Fig. 19; Fig. 2 1 is a perspective view of an exemplary shuttle tray that cooperates with the exemplary frame support base shown in Fig. 20; Fig. 22 is a perspective view of an exemplary shield cask that is mountable onto the exemplary shuttle tray shown in Fig. 21; Fig. 23 is another perspective view of the exemplary remote-controlled molybdenum handling apparatus shown in Fig. 19; Fig.
Load more

Recommended publications
  • PRODUCTION of Mo-99/Tc-99M VIA PHOTONEUTRON REACTION USING
    PRODUCTION OF Mo-99/Tc-99m VIA PHOTONEUTRON REACTION USING NATURAL MOLYBDENUM A Thesis by TALAL BADER HARAHSHEH Submitted to the Office of Graduate and Professional Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE Chair of Committee, Gamal Akabani Co-Chair of Committee, John W. Poston, Sr. Committee Member, Victor M. Ugaz Head of Department, Yassin A. Hassan May 2017 Major Subject: Nuclear Engineering Copyright 2017 Talal Harahsheh ABSTRACT The current shortage of the widely used radionuclide 99mTc has raised many concerns in the nuclear medicine industry. The shortage is caused by the outdated method of production using highly enriched uranium (HEU) and nuclear reactors. This production method is no longer feasible due to the restrictions on the use of HEU. Alternative methods of production must be addressed to ensure the uninterrupted supply of this key radionuclide. This research analyzes an alternative production method of 99mTc using an accelerator-generated 99Mo, which is the parent element of 99mTc. The radionuclide 99mTc has a short half-life of 6 hours. However, 99Mo, the parent nuclide has a much longer half-life of 66 hours. Usually, a medical facility receives a 99Mo/99mTc generator. Technetium-99m would be obtained from the 99Mo provided through chemical separation, which is conducted at the medical facilities. The main issues to be addressed include the production of 99Mo using the photonuclear reaction, the containment and exclusion of unwanted decay products, ensuring the integrity of the end-product 99Mo/99mTc post chemical separation, and assessing the economic feasibility of the complete strategy, including life cycle.
    [Show full text]
  • Supply Security for Medical Radionuclides - Additions 2020 Supplement to RIVM Reports 2019-0101 2017-0063 and 2018-0075
    Supply security for medical radionuclides - additions 2020 Supplement to RIVM Reports 2019-0101 2017-0063 and 2018-0075 RIVM letter report 2020-0171 L.P. Roobol | C.E.N.M. Rosenbaum | I.R. de Waard Supply security for medical radionuclides - additions 2020 Supplement to RIVM reports 2019-0101 2017-0063 and 2018-0075 RIVM letter report 2020-0171 L.P. Roobol | C.E.N.M. Rosenbaum | I.R. de Waard RIVM letter report 2020-0171 Colofon © RIVM 2020 Parts of this publication may be reproduced, provided acknowledgement is given to the National Institute for Public Health and the Environment (RIVM), stating the title and year of publication. DOI 10.21945/RIVM-2020-0171 L. Roobol (author), RIVM C. Rosenbaum (author), RIVM I. de Waard (author), RIVM Contact: Lars Roobol Safety\Measuring and Monitoring [email protected] This study was commissioned by the Ministry of Health, Welfare and Sport within the framework of ad-hoc questions for policy support Published by: National Institute for Public Health and the Environment, RIVM PO Box 1 3720 BA Bilthoven The Netherlands www.rivm.nl/en Page 2 of 77 RIVM letter report 2020-0171 Synopsis Guaranteed supply of medical radionuclides – additions 2020 RIVM has carried out additional research into the guaranteed supply of diagnostic and therapeutic radionuclides for the Netherlands. Radioactive substances can be used for making a diagnosis. There are also radioactive substances that can treat various sorts of cancer, or serve as pain relief, the so-called therapeutic radio-isotopes. Together, these substances are called medical radionuclides. Most of these medical isotopes are made in Europe, in six nuclear reactors, one of which is located in the Netherlands (the HFR).
    [Show full text]
  • The Global Impact of the Mo-99 Shortage
    DOI: 10.26717/BJSTR.2018.04.001114 Michael AB Naafs. Biomed J Sci & Tech Res ISSN: 2574-1241 Review Article Open Access The Global Impact of the Mo-99 Shortage Michael AB Naafs* Dutch Internist-Endocrinologist, International Health Consultancy, Netherlands Received: May 7, 2018; Published: May 25, 2018 *Corresponding author: Michael AB Naafs, Dutch Internist-Endocrinologist, Health Consultant at Naafs, International Health Consultancy, Rhodoslaan 20, and 7577KN, Oldenzaal, The Netherlands Abstract In this mini-review, the history and discovery of molybdene, its use and production, waste problem and alternative cyclotron medical isotope supply further. isotope production are discussed. Definite reactor closing and extensive nuclear construction works in 2018 will comprise global medical Introduction Recently, various reports appeared concerning a global threat- NRC in March 2017, approval to start U.S. production of medical ening shortage of molybdene (1-4).Medical diagnostic imaging Reactor, with its partners, Nordien and General Atomics, filed for isotopes [5]. The start of the renovation in 2018 of the 45-year- old techniques using tehcnetium-99m (99mTC) account for approxi- Petten nuclear reactor in the Netherlands, while simultaneously mately of all nuclear medicine procedures, representing 30-40 mil- starting the experimental Thorium PALLAS project in Patten as lion examinations worldwide every year. Technetium 99 is derived an alternative uranium fuel source, will certainly comprise global from molybdene-99. Disruptions in the supply chain of these med- medical isotope delivery further. In this mini-review the history and ical isotopes, which have half-lives of 66 hours for molybdene-99 discovery of molybdenum, its use and production, waste problems (99Mo) and only 6 hours for 99mTc, and thus must be produced and alternative cyclotron medical isotope production are discussed.
    [Show full text]
  • Research Reactors in France
    Part 2 Research reactors in France Chapter 5 Evolution of the French research reactor “fleet” 5.1. The diversity and complementarity of French research reactors In the IAEA’s Research Reactor Database (RRDB), 42 reactors in France are identified as being research reactors93 (including those no longer in operation, the Jules Horowitz reactor (JHR) which is under construction, and the research reactors at defence-related facilities94). General de Gaulle created the French Atomic Energy Commission (CEA95) by decree in 1945, giving it responsibility for directing and coordinating the development of appli- cations for the fission of the uranium atom nucleus. In this context, a team led by Lew Kowarski started up the first French research reactor in 1948, the ZOÉ atomic pile built at the CEA centre at Fontenay-aux-Roses (figure 5.1). The core of this reactor, consist- ing of uranium oxide-based fuel elements (1,950 kg) sitting in heavy water (5 tonnes) in an aluminium tank surrounded by a 90 cm-thick graphite wall, stood within a 1.5 metre- thick concrete containment wall designed to absorb the different types of ionizing radiation emitted by the nuclear reactions in the core. The ZOÉ reactor was used up to a power of 150 kW to study the behaviour of materials under irradiation, and at 93. This database gives the full list of French research reactors. See also the CEA publication entitled “Research Nuclear Reactors”, a Nuclear Energy Division monograph ‒ 2012, or the publication (in French) “Les réacteurs de recherche” by Francis Merchie, Encyclopédie de l’énergie, 2015.
    [Show full text]
  • (12) Patent Application Publication (10) Pub. No.: US 2013/0301769 A1 Schaffer Et Al
    US 2013 0301769A1 (19) United States (12) Patent Application Publication (10) Pub. No.: US 2013/0301769 A1 Schaffer et al. (43) Pub. Date: Nov. 14, 2013 (54) PROCESSES, SYSTEMS, AND APPARATUS Publication Classification FORCYCLOTRON PRODUCTION OF TECHNETUM-99M (51) Int. Cl. G2G I/00 (2006.01) (71) Applicant: TRIUMF, (US) C2.5D 13/02 (2006.01) (52) U.S. Cl. (72) Inventors: Paul Schaffer, Richmond (CA): CPC ................ G21G I/001 (2013.01); C25D 13/02 Francois Benard, Vancouver (CA); (2013.01) Kenneth R. Buckley, Vancouver (CA); USPC .............................. 376/195; 75/365; 204/507 Victoire Hanemaayer, Richmond (CA); Cornelia Hoehr Manuela, Vancouver (57) ABSTRACT (CA); Julius Alexander Klug, A process for producing technetium-99m from a molybde Vancouver (CA); Michael S. Kovacs, num-100 metal powder, comprising the steps of London (CA); Thomas J. Morley, New (i) irradiating in a Substantially oxygen-free environment, a Haven, CT (US); Thomas J. Ruth, hardened sintered target plate coated with a Mo-100 Vancouver (CA); John Valliant, metal, with protons produced by a cyclotron; Ancaster (CA); Stefan K. Zeisler, (ii) dissolving molybdenum ions and technetium ions from Vancouver (CA); Maurice G. Dodd, the irradiated target plate with an HO solution to form Vancouver (CA) an oxide solution; (iv) raising the pH of the oxide solution to about 14: (73) Assignee: TRIUMF, Vancouver (CA) (V) flowing the pH-adjusted oxide solution through a resin (21) Appl. No.: 13/870,830 column to immobilize KTcO ions thereon and to elute KMoO ions therefrom: (vi) eluting the bound KTcO ions from the resin column; (22) Filed: Apr.
    [Show full text]
  • Evolution of the French Research Reactor “Fleet”
    Chapter 5 Evolution of the French research reactor “fleet” 5.1. The diversity and complementarity of French research reactors In the IAEA’s Research Reactor Database (RRDB), 42 reactors in France are identified as being research reactors93 (including those no longer in operation, the Jules Horowitz reactor (JHR) which is under construction, and the research reactors at defence-related facilities94). General de Gaulle created the French Atomic Energy Commission (CEA95) by decree in 1945, giving it responsibility for directing and coordinating the development of appli- cations for the fission of the uranium atom nucleus. In this context, a team led by Lew Kowarski started up the first French research reactor in 1948, the ZOÉ atomic pile built at the CEA centre at Fontenay-aux-Roses (figure 5.1). The core of this reactor, consist- ing of uranium oxide-based fuel elements (1,950 kg) sitting in heavy water (5 tonnes) in an aluminium tank surrounded by a 90 cm-thick graphite wall, stood within a 1.5 metre- thick concrete containment wall designed to absorb the different types of ionizing radiation emitted by the nuclear reactions in the core. The ZOÉ reactor was used up to a power of 150 kW to study the behaviour of materials under irradiation, and at 93. This database gives the full list of French research reactors. See also the CEA publication entitled “Research Nuclear Reactors”, a Nuclear Energy Division monograph ‒ 2012, or the publication (in French) “Les réacteurs de recherche” by Francis Merchie, Encyclopédie de l’énergie, 2015. 94. This publication does not cover research reactors used for defence-related purposes.
    [Show full text]
  • Graphene—Friend Or Foe? Minor Metals in Nuclear Medicine Chemical Registration in the US—TSCA Reauthorization
    ISSN 2056-6735 (Online) Graphene—Friend or Foe? Minor metals in nuclear medicine Chemical registration in the US—TSCA reauthorization The magazine of the Minor Metals Trade Association 9th Edition 2016/October www.mmta.co.uk 1 THE MMTA’S INTERNATIONAL MINOR METALS CONFERENCE 2017 TAKING PLACE AT THE CONRAD HOTEL, DUBLIN, IRELAND, 24-26 APRIL 2017 Organised by Metal Events Ltd The 2016 conference was our biggest yet. Make sure you are part of the industry's premier event for the minor metals sector with new enhanced MMTA Member Conference Rates for 2017 Be sure to take advantage of the current excellent early-bird rates: MMTA Members will pay the exceptional rate of £600 (+ VAT where applicable) for all registrations received by 28th October 2016 The current fee for Non-Members is £950 (+ VAT where applicable) for all registrations received by 11th January 2017 Non-Members have time to benefit from excellent Member rates by applying for MMTA membership now. To find out more, contact [email protected] To register for the conference or for more information please visit www.metalevents.com or www.mmta.co.uk/conference, or alternatively email [email protected] MMTA Conference Golf Tournament, hosted by ICD Alloys & Metals LLC For our first golf tournament, taking place on Monday 24th April before the start of the conference, we will be at the prestigious K Club, previous venue of the Ryder Cup. The tournament fee of EUR150 (+ VAT) will include transport by coach from and back to the conference hotel, breakfast on arrival, 18 holes of golf, electric buggy, and lunch Registered conference delegates wishing to join this event, should contact [email protected] 2 Speakers for 2017 include: INSIDE THIS ISSUE The MMTA’s Popular Science Talk: Laurence Knight, Producer, BBC World Service, and Andrea Sella, Professor of Inorganic Chemistry, University College London, will take a tour MMTA News & Events 2-4 around some of the amazing minor metals elements that make up our industry.
    [Show full text]
  • List of Nuclear Reactors - Wikipedia, the Free Encyclopedia Page 1 of 37
    List of nuclear reactors - Wikipedia, the free encyclopedia Page 1 of 37 List of nuclear reactors From Wikipedia, the free encyclopedia This List of nuclear reactors is an annotated list of all the nuclear reactors in the world, sorted by country, with operational status. The list includes military, commercial Contents and research reactors, excludes nuclear marine propulsion reactors, except those at land installations, and excludes ■ 1Algeria uncompleted nuclear reactors. ■ 2 Antarctica ■ 3 Argentina ■ 3.1 Power station reactors Algeria ■ 3.2 Research reactors ■ 4Armenia ■ Es Salam (The Peace), 15 MW reactor for research, ■ 5Australia located in Aïn Oussera, in service since 1993 ■ 6Austria ■ Nur, built by Argentine INVAP ■ 7 Bangladesh ■ 8 Belarus Antarctica ■ 9 Belgium ■ 9.1 Power station reactors ■ McMurdo Station – PM-3A NNPU "Nukey Poo" US ■ 9.2 Research Reactors Navy power reactor (operational 1962, shut down ■ 10 Brazil 1972, fully dismantled 1979) ■ 10.1 Research reactors ■ 11 Bulgaria Argentina ■ 12 Canada ■ 12.1 Ontario Power station reactors ■ 12.2 Quebec ■ 12.3 New Brunswick ■ Atucha [5] ■ 12.4 Research reactors (http://www.oni.escuelas.edu.ar/olimpi98/Energia-Vs ■ 13 Chile -Ambiente/atucha1.htm) [6] (http://www.ciencia- ■ 14 China hoy.retina.ar/hoy02/atucha.htm) (Spanish) ■ 15 Colombia ■ 16 Democratic Republic of the Congo ■ Atucha I [7] ■ 17 Cuba (http://www.uic.com.au/nip96.htm) PHWR, ■ 18 Czech Republic 335 MWe ■ 19 Denmark ■ 20 Egypt ■ 21 Estonia ■ 22 Finland ■ 23 France ■ 24 Germany ■ 24.1 Research reactors ■ 24.2 Decommissioned
    [Show full text]