ML19025A265

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Enclosure 2 - Meeting Slides for the January 29 and 30, 2019 Meeting Between Shine Medical Technologies, Inc. and the NRC - Shine Technology Overview
ML19025A265
Person / Time
Site: SHINE Medical Technologies
Issue date: 01/22/2019
From: Van Abel E
SHINE Medical Technologies
To:
Office of Nuclear Reactor Regulation
References
2019-SMT-0006
Download: ML19025A265 (37)
v • d • e


Text

ENCLOSURE 2 SHINE MEDICAL TECHNOLOGIES, INC.

MEETING SLIDES FOR THE JANUARY 29 AND 30, 2019 MEETING BETWEEN SHINE MEDICAL TECHNOLOGIES, INC. AND THE NRC SHINE TECHNOLOGY OVERVIEW PUBLIC VERSION 36 pages follow

SHINE Technology Overview Eric Van Abel, Chief Technical Officer Health. llluminatedT:

Mission Dedicated to being the world leader in the safe, clean, affordable production of medical tracers and cancer treatment elements.

SHINE Medical Technologies I 2

Medical isotopes enable doctors to diagnose and treat illnesses, such as heart disease and cancer SOM+ Procedures Requiring Medical Isotopes Moly-99 Radioactive Decay Tc-99m OTHER*

BONE SCANS OTHER CARDIO Medical Procedure US Medical Procedures Using 99m1c 56,000 Americans Per Day Patient Dose STRESS/REST TEST FOR HEART DISEASE

  • Other includes liver, respiratory, thyroid/ parathyroid, renal, inflammation, tumor imaging, etc.

SH INE Medical Technologies I 3

Located in Janesville, Wisconsin SHINE Medical Technologies I 4

Located in Janesville, Wisconsin Future SHINE Production Facility SHINE Building One SHINE Medical Technologies I 5

SHINE High Level Overview Mo Mo Mo 0

Mo 0

8 LEU is dissolved to form the liquid target Accelerator fires ion beam into tritium gas target chamber 8 Ions from accelerator beam undergo fusion with gas target, freeing neutrons into target solution tank e Uranium undergoes fission in target solution tank, producing Mo-99 and other isotopes e Mo-99 is captured from the solution via an extraction column C, The LEU solution is returned to the target solution tank 23su 99Mo 99mrc Technetium-99m Molybdenum-99

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~ Tc Light Emiting Decay SHINE Medical Technologies I 6

Process Overview 1. Periodic solution preparation from LEU

2. Solution chemistry check and staging
3. Irradiation for 5.5 days
4. Extraction, purification, QC & packaging
5. Periodic cleanup and solution disposal

~~~~~~-4 RECYCLE i---~~~~~-.. ~---+! PRODUCT LOOP

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TARGET SOLUTION PREPARATION PERIODIC PREPARATION HOLD '

TANK :

PERIODIC DISPOSAL WASTE SOLIDIFICATION PERIODIC CLEANUP LOOP SHINE Medical Technologies J 7

Building One

  • Construction complete Q1 2018
  • Full size accelerator demo currently in-progress
  • Radioactive material license by State of Wisconsin
  • Future mockups and prototypes planned
  • Future use for employee training and technology development SHINE Medical Technologies I 8

Top Long-Lead Process Equipment Items

  • Supercell
  • Neutron Flux Detectors
  • Safety l&C System (TRPS/ESFAS)
  • Neutron Drivers (Accelerators)
  • Thermal Cycle Absorption Process (TCAP) Equipment
  • Radioactive Liquid Waste Immobilization System SHINE Medical Technologies I 9

Technological Approach

  • Small systems: Hundreds of times less power than isotope production reactors being used Low source term-helps ensure safety of public and workforce Decay heat per system < 1 kW within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Minimizes waste nuclide generation compared to reactors
  • Low enriched uranium (LEU) reusable target Reduces waste Product compatible with current supply chain Eliminates need for HEU
  • Driven by low-energy electrostatic accelerator Eliminates need for HEU
  • Multiple units and trains provide operational scalability and flexibility

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SHIN E Medical Technologies 110

Safety Philosophy

  • Low decay heat, low pressure, low temperature system
  • Minimal stored energy
  • Independent units limit common cause failures
  • Operator actions are not required for safe response to an accident
  • In the event of an upset condition:
  • TSV reactivity protection system (TRPS) initiates trip of system
  • Two completely independent safety-related TSV dump valves open
  • Target solution gravity drains to the TSV dump tank (criticality safe at all uranium concentrations)
  • Hydrogen concentration is maintained below LFL by off-gas system blowers
  • Following UPS battery run time, entire plant is passively safe
  • 90 days without cooling: Pool temperature rise is less than approximately 12°F

Security-Related Information - Withheld Under 10 CFR § 2.390 Facility Layout - General Arrangement Security-Related Information SHINE Medical Technologies 112

Security-Related Information - Withheld Under 10 CFR § 2.390 Facility Layout - General Arrangement Security-Related Information SHINE Medical Technologies 113

Security-Related Information - Withheld Under 10 CFR § 2.390 Facility Layout - General Arrangement - Mezzanine Security-Related Information SHINE Medical Technologies J14

Facility Layout - Elevation and Section Views 1.0 ~t,oc:

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,~ ~ r - f...,._.,c;:: a:::r ;.._ -~ID-ct,:.L WEST BUii DING ELEVATION SHINE Medical Technologies 11 5

Security-Related Information - Withheld Under 10 CFR § 2.390 Facility Layout - Elevation and Section Views Security-Related Information SHINE Medical Technologies 116

Security-Related Information - Withheld Under 10 CFR § 2.390 Facility Layout - Elevation and Section Views Security-Related Information SHINE Medical Technologies 117

Major Process Equipment

  • Subcritical Assembly and TSV Off-Gas System
  • Neutron Driver
  • Extraction and Purification Process
  • Supercell
  • Radioactive Waste Handling rn TARGET SOLUTION PREPARATION PERIODIC PREPARATION.....................

PERIODIC CLEANUP LOOP SHINE Medical Technologies 118

Proprietary Information - Withheld from Public Disclosure Under 10 CFR § 2.390(a)(4)

Subcritical Assembly Overview

  • Hybrid fusion-fission device
  • Accelerator generates fusion neutrons from D-T reaction
  • Subcritical assembly takes fusion neutrons, slows them down, and multiplies them through fission reactions
  • Process
  • Fast neutrons created in center of assembly (neutron spark plug)
  • Neutrons pass through [Proprietary Information] multiplier
  • Multiplied neutrons pass into uranium solution in TSV, where they are absorbed by uranium and cause fission
  • Transfer solution to the processing facility for isotope removal Proprietary Information Subcritical Assembly with Accelerator Target Assembly SHINE Medical Technologies 119

Low energy, inherently-safe system

  • Key parameters:
  • Pressure: Below atmospheric
  • Target solution: Uranyl sulfate
  • Low temperature:< 212°F
  • Low fluid flow rates: Natural circulation of target solution
  • Reactivity: Subcritical SHINE Medical Technologies 120

Proprietary Information - Withheld from Public Disclosure Under 10 CFR § 2.390(a)(4)

Subcritical Assembly - Design Summary Proprietary Information Subcritical Assembly with Accelerator Target Assembly

  • Skid-fabricated components
  • Safety-related to retain target solution in proper geometry
  • Target solution pressure boundary principally constructed of Type 347 stainless steel
  • Designed for 100 psig SHINE Medical Technologies J21

Proprietary Information - Withheld from Public Disclosure Under 10 CFR § 2.390(a)(4)

TSV Offgas System (TOGS)

  • The TOGS sweeps gas through the TSV heads pace
  • Operates during irradiation to remove and recombine hydrogen and oxygen
  • Sweep gas passed over catalytic recombiner beds to form water vapor
  • Water vapor generated by the TSV and the recombiner beds is condensed and returned to the TSV Proprietary Information SHINE Medical Technologies 122

Proprietary Information - Withheld from Pu blic Disclosure Under 10 CFR § 2.390(a)(4)

TSV Offgas System (TOGS)

  • TOGS general parameters
  • Sweep gas flowrate: [Proprietary Information]
  • Design nominal hydrogen concentration: [Proprietary Information]
  • Liquid return rate: [Proprietary Information]
  • Recombiner materials: [Proprietary Information]
  • Safety-related functions to ensure hydrogen concentrations remain acceptable

Proprietary Information - Withheld from Public Disclosure Under 10 CFR § 2.390(a)(4)

Neutron Driver

  • Neutron driver is hydrogen particle accelerator
  • Supplied by Phoenix
  • 300 kV constant voltage (static)

Accelerates hydrogen isotopes to a gas target chamber

  • Deuterium-deuterium reaction produces

-1 % output Deuterium-tritium reaction produces

-100% output

  • Neutron source to drive the subcritical chain reactions
  • Operation is not safety function
  • Turning off accelerator is a safety function Safety-related breakers isolate power feed to accelerator high voltage power supply Proprietary Informat ion SHINE Medical Technologies 124

Security-Related Information - Withheld Under 10 CFR § 2.390 Tritium Purification System (TPS) Overview

  • Function: Continuously supply purified tritium (target gas) and deuterium (source gas) to neutron drivers
  • Uses Thermal Cycling Absorption Process (TCAP) technology IP Licensed from Savannah River National Laboratory
  • Key features
  • Semi-continuous operational mode (batched gas chromatography)
  • 1 TPS serves up to 8 drivers
  • Tritium maintained sub-atmospheric outside of glovebox Security-Related Information SHINE Medical Technologies 125

Proprietary Information - Withheld from Public Disclosure Under 10 CFR § 2.390(a)(4)

Major TPS Equipment and Functions

  • TPS process equipment and main glovebox Remove impurities Separate tritium and deuterium Confine tritium Process equipment normal ly contains t ritium Glovebox confines in the event of a release
  • ATIS skids and gloveboxes Distribute gases via headers Interface with neutron drivers and regulate flow to a neutron driver Confine tritium
  • Stripper system & air hood Remove residual tritium that enters glovebox atmosphere Proprietary Information SHINE Medical Technologies J26

Proprietary Information - Withheld from Public Disclosure Under 10 CFR § 2.390(a)(4)

Security-Related Information - Withheld Under 10 CFR § 2.390 TPS Flow Diagram (Production Facility)

Proprietary Information Security-Related Information SHINE Medical Technologies 127

Proprietary Information - Withheld from Public Disclosure Under 10 CFR § 2.390(a)(4)

Overview of Mo-99 Separation Process

  • Target solution transferred from IU cell to hot cells via vacuum lift system
  • Mo-99 separated from target solution by extraction column
  • [Proprietary Information]
  • [Proprietary Information]
  • [Proprietary Information]
  • Mo-99 solution evaporated and transferred to purification process Proprietary Information Mo-99 Extraction Equipment SHINE Medical Technologies 128

Overview of Mo-99 Purification Process

Modified Cintichem Process

  • Developed by Argonne National Laboratory for the Department of Energy
  • Cintichem is a long-established process
  • Used at the Cintichem facility in Tuxedo, NY until 1989
  • Process perform by manipulators in hot cell
  • Precipitation and filtration of contaminants
  • Adsorption and filtration of contaminants on charcoal columns

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SHINE Medical Technologies 129

Proprietary Information - Withheld from Public Disclosure Under 10 CFR § 2.390(a)(4)

Supercell Proprietary Information 11 Redundancy is included to handle the 8 irradiation cells and provide flexibility in operations Proprietary Information SHINE Medical Technologies 130

Proprietary Information - Withheld from Public Disclosure Under 1 O CFR § 2.390(a)(4)

Supercell Design

  • Safety function to confine radioisotopes upon release
  • Confinement limits release to stack and to Radioisotope Production Facility (RPF) area
  • Provides biological shielding for workers
  • Criticality safety controls incorporated Proprietary Information SHINE Medical Technologies 131

Waste Treatment

  • Waste Stream Overview
  • Three types of radioactive waste:

As generated solid radioactive waste, including spent adsorption columns Solidified radioactive waste Gaseous wastes

  • Liquid waste is collected in tanks with and without critically-safe geometry, depending on liquid waste stream
  • Size and configuration of liquid waste tanks provide for operational flexibility and reduction in waste source term
  • Liquid waste streams are analyzed and blended to allow for solidification in cement and acceptance at a licensed burial facility
  • Waste streams are solidified in a sealed solidification skid maintained at a slight negative pressure compared to the surrounding Radioisotope Production Facility SHINE Medical Technologies 132

Proprietary Information - Withheld from Public Disclosure Under 10 CFR § 2.390(a)(4)

Solid Wastes Exported to Storage Drums Proprietary Information SHINE Medical Technologies 133

Security-Related Information - Withheld Under 1 O CFR § 2.390 Radioactive Liquid Waste Storage System Security-Related Information SHINE Medical Technologies J34

Proprietary Information - Withheld from Public Disclosure Under 10 CFR § 2.390(a)(4)

Radioactive Liquid Waste Immobilization System

  • Receives liquid wastes from the plant and solidifies them in a cement-based mixture
  • Drums are cured and transported to on-site staging building, prior to offsite shipment
  • Waste system is skid-mounted and assembled Proprietary Information SHINE Medical Technologies 135

Proprietary Information - Withheld from Public Disclosure Under 1 O CFR § 2.390(a)(4)

Gaseous Waste Treatment Proprietary Information SHINE Medical Technologies 136

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