ML19025A265
| 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) | |
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 OTHER*
Isotopes STRESS/REST TEST FOR HEART DISEASE US Medical Procedures Using 99 m1c 56,000 Americans Per Day BONE SCANS OTHER CARDIO Radioactive Medical Decay Procedure Moly-99 Tc-99m Patient Dose
- 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 SHINE Future SHINE Building One Production Facility SHINE Medical Technologies I 5
SHINE High Level Overview 0 LEU is dissolved to form the liquid target e Uranium undergoes fission in target solution tank, producing Mo-99 8 Accelerator fires ion and other isotopes beam into tritium gas target chamber e Mo-99 is captured from Mo 8 Ions from accelerator the solution via an extraction column beam undergo fusion with gas target, freeing C, The LEU solution is Mo neutrons into target returned to the target solution tank solution tank Mo 23su 99Mo 99mrc Technetium-99m 0
Molybdenum-99
- ~ ~ Tc Mo Light Emiting Decay SHINE Medical Technologies I 6
Process Overview
- 1. Period ic solution preparation from LEU ~~~~~~-4 RECYCLE i - - - ~ ~ ~ ~ ~ - . . ~---+! PRODUCT LOOP
- 2. Solution chemistry check and staging
- 3. Irradiation for 5.5 days
- 4. Extraction, purification, QC & packaging [I] PERIODIC TARGET SOLUTION DISPOSAL PREPARATION
- 5. Period ic cleanup and WASTE SOLIDIFICATION solution disposa l HOLD '
TAN K : *
.............. PERIOD IC PRE PARATION 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
- 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 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-Re lated 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 Un der 10 CFR § 2.390 Facility Layout - General Arrangement - Mezzanine Security-Re lated Information SHINE Medical Technologies J14
Facility Layout - Elevation and Section Views 1.0 ~t,oc:
~
rt" *-r
_, l 11 I
I
,{
I/
V
~ --- - --- ---- -- - - -- -- - -- ----
V I/
/ /
/
-~a :,~ *~f r. . ;
~r- ~ liH ~ f.}~
,._.,c;:: a:::r ;. _ -~ID- ct,:.L .4JLJE] ~ -Jtl[f I rt I I I I I If t Q 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-Re lated Information SHINE Medical Technologies 117
Major Process Equipment
- Subcritical Assembly and TSV Off-Gas System
- Neutron Driver
- Tritium Purification System
- Extraction and Purification Process
- Supercell
.... . ............... . 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) Proprietary Information
- 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 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
Propriet ary Information - Withheld from Pub li c Disclosure Under 10 CFR § 2.390(a)(4)
Subcritical Assembly - Design Summary
- 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 Prop ri etary Information Subcritical Assembly with Accelerator Target Assembly 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
- Sweep gas passed over catalytic recombiner beds to form water vapor Prop ri etary Information
- Water vapor generated by the TSV and the recombiner beds is condensed and returned to the TSV SHINE Medical Techno logies 122
Propriet ary Informatio n - Wit hhel d from Pu blic Disclosure Und er 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: [Proprieta ry Information]
Prop rietary Information
- Safety-related functions to ensure hydrogen concentrations remain acceptable
- Operates on UPSS power for minutes following loss of offsite power to recombine decay hydrogen TOGS Skid SHINE Medical Technologies 123
Prop rietary Info rm atio n - Withh eld 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 Pro prietary Info rm at ion
- 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 iso late power feed t o accelerator high voltage power supp ly SHINE Medical Technologies 124
Security-Related Inform ation - With held 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 (batc hed gas chromatography)
- 1 TPS serves up to 8 drivers Secu rity-Related Inform ation
- Tritium maintained sub-atmospheric outside of glovebox SHINE Medical Tec hnologies 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 Proprietary Information
- 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 SH IN E Medical Technologies J26
Proprietary Information - Withheld from Publ ic Disclosure Under 10 CFR § 2.390(a)(4)
Security-Related Info rmati on - Withheld Und er 10 CFR § 2.390 TPS Flow Diagram (Production Facility)
Proprietary Information Security-Related Information SHINE Medical Technologies 127
Proprietary Information - Wit hheld from Pub lic Disclosu re Un de r 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
- [Proprietary Information]
- Mo-99 solution evaporated and transferred to purification process 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
- Complexation of molybdenum
- Adsorption and filtration of contaminants on charcoal columns SH INE Medical Tec hnologies 129
Proprietary Information - Withheld from Public Disclosure Under 10 CFR § 2.390(a)(4)
Supercell Proprietary Information Proprietary Information 11 Redundancy is included to handle the 8 irradiation cells and provide flexibility in operations SHINE Medical Technologies 130
Proprietary Information - Withheld from Public Disclosure Under 10 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 Proprietary Information
- Criticality safety controls incorporated 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 10 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 10 CFR § 2.390(a)(4)
Gaseous Waste Treatment Proprietary Information SHINE Medical Technologies 136