The Current State of Mo-99 Supply and the Conversion to LEU

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1 The Current State of Mo-99 Supply and the Conversion to LEU

2 Target Audience: Pharmacists ACPE#: L04-P Activity Type: Knowledge-based Target Audience: ACPE#: Activity Type: 22

3 Disclosures Roy W. Brown is a full time employee of Curium. Curium is a leading producer of diagnostic and therapeutic radiopharmaceuticals for the global market. Target Audience: ACPE#: 33 Activity Type: The American Pharmacists Association is accredited by the Accreditation Council for Pharmacy Education as a provider of continuing pharmacy education.

4 Activity Type: Learning Objectives 1. Understand the current reactors irradiating targets for Mo-99 production. 2. Understand who the global Mo-99 producers are. 3. Explain Target the Audience: process of conversion from HEU to LEUproduced Mo Understand ACPE#: the alternate Mo-99 production technologies under development. 44

5 1. Assessment Question 1. Name the four major Mo-99 producers? A. ANSTO, Curium, Nordion, and NTP B. Curium, IRE, Nordion, and NTP C. ANSTO, Curium, IRE and NTP Target Audience: D. IRE, NTP, GE and ANSTO ACPE#: Activity Type: 55

6 2. Assessment Question 2. What is the reason for the conversion from High Enriched Uranium (HEU) to Low Enriched Uranium (LEU)? A. It is more cost effective to produce Mo-99 with LEU. B. More Target reactors Audience: are able to irradiate LEU targets than HEU. C. The U.S. and other governments are trying to enhance global security ACPE#: by reducing the use of HEU. Activity Type: 66

7 3. Assessment Question 3. What continent currently produces the most Mo-99? A. North America B. Asia C. South Africa Target Audience: D. Europe ACPE#: Activity Type: 77

8 The Current State of Mo-99 Supply and the Conversion to LEU The Current Supply of Mo-99 8

9 Mo-99 Process Flow Uranium is shipped from U.S. to target manufacturer in France Uranium is fabricated into targets Unirradiated targets are transported to reactors BR2 reactor HFR DE PO Maria reactor FR CERCA Finished Mo-99 is flown to U.S. Mo-99 is extracted from targets and purified Targets are irradiated about 160 hours 9

10 Global Mo-99 Production Targets arriving at the reactor contain U-235 Manufacturers buy reactor slot time for processing Targets placed in slot near the core of the reactors for bombardment for about one week After irradiation the targets are highly radioactive and after cooled are transported to the processing facility This weekly irradiation will typically provide a Mo-99 producer enough material to provide the generator manufacturer enough material for each run that week Isotope table in reactor pool Photo courtesy of NRG 10

11 Mo-99 Target Irradiation All reactors are in the process of converting to plate type targets Targets have aluminum cladding around layer of uranium Fission of U-235 produces products with atomic mass peaks at 95 and HFR Target Assembly Fuel Rod Photo courtesy of NRG

12 Nuclear Reactor Core 12 Photo courtesy of NRG

13 The Current State of Mo-99 Supply and the Conversion to LEU The Current Reactors Used to Irradiate Targets for Mo-99 Production 13

14 The Six Main Mo-99 Reactors Image used with permission. Image used with permission. Credit photo: ANSTO SAFARI-1 Reactor South Africa Maria Research Reactor Poland OPAL Reactor Australia Credit photo: NMS. Image used with permission LVR-15 REZ Reactor Czech Republic Credit Photo: NRG. High Flux Reactor (HFR) The Netherlands - The HFR is property of the European Commission and is operated by the Nuclear Research and Consultancy Group (NRG). Nuclear Research Centre s Belgian Reactor 2 (BR2) Belgium 14

15 Global Reactor Locations HFR Maria BR-2 LVR-15 SAFARI-1 OPAL 15

16 Overview: World Global Reactors Producing Mo-99 Country Reactor Mo-99 Producer Using Reactor Year Reactor Commissioned The Netherlands HFR IRE 1961 The Netherlands HFR Curium 1961 Belgium BR-2 IRE 1961 Belgium BR-2 Curium 1961 South Africa SAFARI NTP 1965 Australia OPAL ANSTO 2007 Poland Maria Curium 1974 Czech Republic LVR-15 REZ IRE

17 Reactor Maintenance Routine maintenance: All of the major isotope producing reactors consult each other before developing maintenance schedules to minimize down-time Various reactors have different requirements for scheduled maintenance Scheduled maintenance reduces unplanned outages Unscheduled maintenance: Unplanned down-time leads to most isotope shortages Unplanned outages at NRU and HFR led to wide spread shortages of Mo-99 in 2009 and 2010 The age of the major isotope producing reactors has led to an increasing amount of unscheduled maintenance 17

18 Curium s Mo-99 Processing Facility in Proximity to the HFR Mo-99 Processing Facility HFR 18

19 The Current State of Mo-99 Supply and the Conversion to LEU The Global Mo-99 Processors 19

20 2010 Google Image, 2010 Tele Atlas, 2010 Aerodata International Surveys 2010 Google Image, 2010 DigitalGlobe Global Mo-99 Processors Curium Located in The Netherlands. Nuclear Technology Products (NTP) Located in South Africa. The Institute for Radio Elements (IRE) Located in Belgium. Australian Nuclear Science and Technology Organization (ANSTO) Located in Australia 2010 Google Image, 2010 DigitalGlobe Credit photo: ANSTO 20

21 Global Mo-99 Processing Locations Curium IRE NTP ANSTO 21

22 Molybdenum Facility Hot Cell 22 Curium s Mo-99 Production Facility in the Netherlands

23 Inside the Hot Cell Moly processing facility hot cell 23

24 Mo-99 Processing Diagram Alkaline Target Dissolution Process: Dissolve in NaOH Aluminum Clad Target Sodium Hydroxide is used to dissolve the entire target Filtration NaAlO 2 & Na 2 MoO 4 Solution is filtered to remove suspended solids Sorbent filters selectively remove the molybdate ion NH 4 OH Removal of MoO -2 4 Molybdate washed with Ammonium Hydroxide and dissolved in Sodium Hydroxide Dissolved in NaOH Na 2 MoO 4 24

25 25 Curium s Mo-99 Raw Material Supply

26 Capacity and Reliability Investments 26 Curium has taken steps to increases Mo-99 production capacity and supply reliability Modifying target rigs in reactors to increase irradiation capacity Enhancing ability to transport irradiated targets Increasing the numbers of irradiated targets processed during a single Mo-99 production run to augment capacity Adding a fifth Mo-99 production day to increase capacity by 20% Contracting for extra irradiation positions with reactor partners (Outage Reserve Capacity) Maintaining diversity of supply by contracting with multiple reactors for irradiation of targets and retaining supply agreements with other Mo-99 processors Complying with U.S. government mandate to transition from the use of High Enriched Uranium (HEU) to Low Enriched Uranium (LEU) for Mo-99 production and support global non-proliferation efforts which was achieved at the beginning of 2018 Other Mo-99 processors are also dedicated to reliability and have been taking similar steps to ensure patients around the world continue to have access to medical isotopes for nuclear medicine

27 The Current State of Mo-99 Supply and the Conversion to LEU The Tc-99m Generator Producers 27

28 Global Generator Manufacturing Locations GE Healthcare & Biosciences Curium Curium Lantheus Medical Imaging Polatom Curium NTP ANSTO 28

29 Mo-99 Producers Panel at 2017 SNMMI Meeting All four Mo-99 producers participated on a panel at the annual meeting to summarize steps they had taken to increase reliability of supply. Increased reliability has been achieved through increased capacity, on-going maintenance and investment, and global cooperation. It s clear that the world s Mo-99 producers have collaboratively used innovation, technology and careful planning to increase capacity and safeguard supplies of this critical medical isotope, said SNMMI President Sally Schwarz. 29

30 The Current State of Mo-99 Supply and the Conversion to LEU The Conversion from HEU to LEU-Produced Mo-99 30

31 The Transition from HEU to LEU Uranium isotope used for fission is U Low-enriched uranium (LEU) is defined as U-235 < 20% 3 Highly-enriched uranium (HEU) is defined as U % 3 Most HEU targets used in medical isotope production is > 90% U Non-HEU based Mo-99 produced in a manner not using HEU (i.e., LEU-based, accelerator production, neutron capture) 1 U.S. Department of Energy (DOE) is advocating removal of all HEU from medical isotope production to enhance global security 1 Medical radioisotope industry is converting the Mo-99 production process to the use of LEU Multiple cost components related to development and use of new LEU targets upfront development, facility modifications, regulatory, operational, waste management/disposal Conversion to LEU targets will lead to inherent loss of efficiency conversion from 93% to < 20% U-235 enrichment (lower target yields) World-nuclear.org. Radioisotopes in Medicine Nuclear Medicine Available at: Accessed December 8, World-nuclear.org. Uranium Enrichment Enrichment of uranium Available at: Accessed December 8, World-nuclear.org. World Nuclear Association Glossary Available at Accessed December 8, 2015.

32 Status of LEU Conversion Efforts for Current Mo-99 Producers Latest conversion update ANSTO Began operation with LEU Targets Jan 2016 Jan 2017 Jan 2018 Jan 2019 NTP Fully Converted to LEU Mo-99 now Fully Converted to LEU as of May, 2017 Curium Fully Converted to LEU Mo-99 now Target and radiochemistry finalized Fully Converted to LEU as of Jan, 2018 IRE In process of converting to LEU targets Target and radiochemistry finalized Expect to be Converted very late 2018, or

33 The Current State of Mo-99 Supply and the Conversion to LEU Alternate Production Methods for Mo-99 33

34 NorthStar Radiogenix Generator NorthStar Medical Isotopes is awaiting FDA approval, expected sometime in The generator column is designed to retain the Tc-99m, rather than Mo-99. They state they will be able to produce 1000 Ci/wk using natural Mo-98 targets irradiated at MURR. NorthStar has received $25 million (matching) grants from DOE for their project. They plan to produce Mo-99 on e-beam accelerators with Mo-100 targets in the future. Courtesy of NorthStar 34

35 General Atomics/Nordion/MURR General Atomics (GA) has developed a Selective Gaseous Extraction (SGE) process in which Mo-99 is chemically extracted from modified Uranium fuel. They plan to use the Missouri University Research Reactor (MURR) reactor for the SGE process. The Mo-99 will be extracted in Columbia, MO and then sent to Nordion for further processing. DOE has provided GA/Nordion $25 million (matching) in grants for the project. They have stated they will have Mo-99 for testing in Courtesy of General Atomics

36 Morgridge/SHINE Mo-99 Production SHINE (Subcritical Hybrid Intense Neutron Emitter) unit is expected to produce day Ci/week. They have received $25 million (matching) grants from DOE. Microwaves ionize deuterium gas which strikes tritium gas generating neutrons. Neutrons are multiplied, and then strike LEU target solution. SHINE has begun construction on a Pilot Plant for demonstration of their technical process. Courtesy of Morgridge/SHINE 36

37 Northwest Medical Isotopes (NWMI) NWMI has developed a propriety process to produce uranium dioxide microspheres. They plan to irradiate the microspheres in university reactors (MURR & OSU). They will dissolve the irradiated microspheres, extract the Mo-99, and then recycle the uranium. Their process eliminates the majority of the radioactive waste and reduces uranium costs. The NWMI construction permit from NRC is expected to be issued in early UO 3 microspheres Image Courtesy of NWMI They plan to be in operation in

38 Niowave Niowave plans to use a superconducting electron beam accelerator to fission LEU. They plan to accelerate electrons and then brake them with lead-bismuth alloy, causing the emission of a photon. The uranium will undergo photon-fission producing Mo-99 and all of the conventional fission products. One 40 MeV, 100kW accelerator will be able to produce 1500 Ci per week. Electron Beam Accelerator They announced in 2017 that they had successfully produced a small Mo-99 sample. Their estimated costs and timelines have not been made public. Niowave s Facility in Lansing, MI 38

39 Tc-99m Production on PET Cyclotrons Several groups in Canada and Europe are exploring Tc-99m production on PET cyclotrons. The cyclotrons need to be 18 MeV or greater and higher beam current for efficient production. Enriched Mo-100 targets are used, but they produce impurities of Tc-93, Tc-93m, Tc-94, Tc-94m, Tc-95, Tc-96, Tc- 96m, Tc-97m. These impurities have t 1/2 up to 4 days, can contribute to patient dose and degrade the image. TRIUMF s Mo-100 Target Univ of Nottingham's Separation Module The cost per mci to produce Full Cost Recovery Tc-99m in this manner is still not clear. The regulatory pathway for this Tc-99m is not clear. 39 Images Courtesy of TRIUMF and Univ. of Nottingham

40 The Current State of Mo-99 Supply and the Conversion to LEU SUMMARY 40

41 Summary All of the global Mo-99 producers have made significant improvements in production capacity. Even though additional capacity has increased reliability, unplanned shutdowns still may occur, which could impact some generator manufacturers. The global Mo-99 producers have been working very hard to convert from HEU to LEU, and everyone should be completed in Several alternate Mo-99 producers continue to do development work using a variety of different technologies. 41

42 1. Assessment Question 1. Name the four major Mo-99 producers? A. ANSTO, Curium, Nordion, and NTP B. Curium, IRE, Nordion, and NTP C. ANSTO, Curium, IRE and NTP Target Audience: D. IRE, NTP, GE and ANSTO ACPE#: Activity Type: 42

43 2. Assessment Question 2. What is the reason for the conversion from High Enriched Uranium (HEU) to Low Enriched Uranium (LEU)? A. It is more cost effective to produce Mo-99 with LEU. B. More Target reactors Audience: are able to irradiate LEU targets than HEU. C. The U.S. and other governments are trying to enhance global security ACPE#: by reducing the use of HEU. Activity Type: 43

44 3. Assessment Question 3. What continent currently produces the most Mo-99? A. North America B. Asia C. South Africa Target Audience: D. Europe ACPE#: Activity Type: 44