ML15084A267
| ML15084A267 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 01/31/2015 |
| From: | Haass C C Northwest Medical Isotopes |
| To: | Reese S Office of Nuclear Reactor Regulation, Oregon State University |
| Shared Package | |
| ML15084A262 | List: |
| References | |
| NWMI-LTR-002, NWMI-LTR-2015-003 | |
| Download: ML15084A267 (8) | |
Text
- NWMINORTHWEST MEDICAL ISOTOPESATTACHMENT 3Northwest Medical Isotopes, LLCSupplementary information supporting the license amendment application for thepurpose of demonstrating 99M0 production capability in the OSTRPublic VersionInformation is being provided via hard copy
"""" NW MI**. 0O .NORTHWEST MEDICAL ISOTOPESJanuary 31, 2015NWMI-LTR-002 Oregon State University Steve Reese, Radiation Center Director100 Radiation CenterCorvallis, OR 97331-5903 RE: TRANSMITTAL OF LOW ENRICHED URANIUM OFF-GAS RESULTS COMPLETED AT THEUNIVERSITY OF MISSOURI RESEARCH REACTORNorthwest Medical Isotopes, LLC (NWMI) is pleased to transmit the results of the off-gas results resulting fromthe irradiation of low enriched uranium (LEU) at the University of Missouri Research Reactor.
LEUprovided by NWMI , LEU Test #1 were irradiated in the MURR reactor from December 8 through15, 2014. After irradiation, the target was punctured and off-gas analysis was performed.
The irradiated targetwas then opened and the of the target. The LEUThe aluminum irradiation can inspected and no damage to the canThe results of the off-gas analysis indicate that collected 133Xerepresents of the -Xe produced in the sample.If you have any questions, please contact me on 509-430-6921.
Sincerely, Carolyn HaassVice President cc: Todd Keller, OSTRNorthwest Medical Isotopes, LLC 1 815 NW 9th Ave, Suite 256 iCorvallis, OR 97330 University of Missouri-Columbia 1513 Research Park Dr.Research Reactor Center Columbia.
MO 65211Phone: (573) 882-5287Fax: (573) 882-6360MansonLmniissouri.edu January 29, 2015To: Carolyn HaassNorthwest Medical Isotopes, LLCFrom: Leo MansonUniversity of Missouri Research Reactor (MURR)Re: Low Enriched Uranium (LEU I rradiation and Post Irradiation Evaluation (PIE) Results for I LEU Iprovidead by Northwest Medical Isotopes, LLC.Summary Comments:
LEU provided by Northwest Medical Isotopes, LLC(NWMI) ,LEU Test #1 were irradiated in the MURR reactor from December 8 through 15,2014. After irradiation, the target was punctured and off-gas analysis was performed.
TheTe aluminumiraito a npce and no damage to thencan Tr] Theresults of the off-gas analysis indicate that collected Xe represents of the '33Xeproduced in the sample.Detailed Report: ý of low enrichment uranium (LEU) supplied byNWMI was encapsulated in a specially designed=
aluminum container and irradiated for153.86 hours9.953704e-4 days <br />0.0239 hours <br />1.421958e-4 weeks <br />3.2723e-5 months <br /> in position K2 in the graphite reflector region of the MURR reactor.
The irradiation began on 08 December 2014 and ended at 2:00 AM on 15 December 2014.The sample was transferred to Hot Cell 09 (HC-09) for processing at -3:00 PM on 16 December2014. An air monitoring system (Eberline AMS-4, Serial Number 1173, Calibrated on 10/10/14) was used to monitor for airborne radioactive material from the exhaust of HC-09. The AMS-4sampled the exhaust ventilation after (downstream from) the two HEPA and three carbon filters onHC-09.Target Piercing and Gas extraction:
On 17 December 2014, the target was positioned in aninstrument within HC-09 designed to create two sealed punctures in the outer aluminum wall ofthe target can providing a path for helium (He) purge gas to sweep any free fission gasses out ofthe can and into a cryogenically cooled gas trap for analysis.
Helium (He) gas purged through thealuminum target can, and data was collected to determine determine the release of Xe- 133 gasfrom the target can. Details of the design of the detector and collection trap and test results arepresented in (Attachment 1).The target was removed from the gas extraction apparatus, and the top of the target container wascut off, first cutting theNWMI LEU#1 Off-Gas Results -17 December 2014 Page 1NWMI LEU#1 Off-Gas Results -17 December 2014Page 1 University of Missouri-Columbia Research Reactor Center1513 Research Park Dr.Columbia.
MO 65211Phone: (573) 882-5287Fax: (573) 882-6360MansonL(cmnissouri.edu her, the irradiation can and can-lid were visually inspected and there was no indication ofNo elevation of the background n the AMS-4 was observed when the =the glass vial or theAttachments:
- 1. Fission Gas Extraction and ResultsNWMILEU1 Of-Ga Reult -1 Deembr 204 Pge INWIVII LEU#1 Off-Gas Results -17 December 2014Page 2t NWMI LEU #1 Off-Gas Results -Attachment IAttachment 1Fission Gas Extraction Design, Calibration and ResultsDesign: A custom designed purge and trap system using an inert sweep gas flowing through thetarget cavity and into a cryogenic trap allowing immediate measurement of trapped fissiongasses. Helium (He) is used to purge fission gasses from the target cavity, and transfer thegasses to a condenser/carbon-filter (gas trap) surrounded by isolating shielding and a cryogenic cooling which effectively traps the fission gasses.A specialized puncturing device was deminimal or no loss of contained
,asses.W1111 litlltIILailling ia tLU aiItW4tograph of the puncturing devicethe tission gasses to be ettliis shown below in Figure 1.Figure 1. Photograph of puncture device with outer can wall for testing.Page 1 of 4 NWMI LEU #1 Off-Gas Results -Attachment IThe fission gas trap (Figure 2), designed to condense and hold fission gasses during analysis, consists of copper tubing with a collection section loaded with activated carbon (NUSORBKITEG from NUCON International, Inc.). Approximately
ý of activated carbon isloaded into a M diameter, by = long section tube. While the carbon provides a highsurface area for collection, the primary trapping of fission gas is conducted through cryogenic cooling.
During use, the condenser/filter "trap" is submerged in liquid nitrogen which condenses and maintains fission gasses on the carbon during analysis.
Heat tape, and an insulator are usedto prevent early trapping of the gasses allowing the trapped gas to be concentrated on the carbonwhere it can be analyzed.
Thermocouples (TC-1 and TC-2) used to monitor and allowadjustment of temperatures in both the chilled and heated ranges.Figure 2. Diagram and Photo of Condenser/Trap Calibration:
Xenon, specifically 133Xe, was chosen for quantifying fission gas release because itis inert and provides a countable gamma ray emission at 81 keV and is readily available inmedical dose quantities that are ideal for our calibration comparison work. The overallefficiency of the system for collecting and measuring Xe-133 was determined using known 133Xesources from Lantheus Medical Imaging Inc. (LMI), (Lot XG-2236).
The '33Xe activity collected on the liquid nitrogen cooled activated carbon was measured using aHPGe detector (Canberra Model GC2018) and Inspector 2000 digital signal processor configured as presented in Figure 3.Page 2 of 4 nt IHelium gas (flow rate of .) was used to purge the 133Xe from the glass vial calibration sources transferring it to the trap where flow of liauid nitrogen was adjusted to maintain aconstant temperature of approximately on the copper housing of the trap to holdthe gas on the trap during assay. Five minute gamma spectrum counts were repeatedly taken asthe gas collected on the trap until an accumulation plateau was achieved, Figure 4. Afterapproximately 10 minutes, count rates plateaued and remained stable until the carbon trap wasallowed to warm. The detector with trap was calibrated with M of 133Xe calibrated forNoon 10 December 2014 (LMI, Lot XG-2236).
The calibration response factor for thedetector/trap system was 133Xe.Figure 4. NWMI LEU Test #1 Gas Calibration Plot 133Xe (counts/300 seconds vs count #)Page 3 of 4 NWMI LEU #1 Off-Gas Results -Attachment ITesting Results:
Helium (He) gas purged through the aluminum target can, containing irradiated LEU ý, efficiently transferred various fission gasses from the target to acryogenically cooled carbon filter where the 133Xe is counted and quantified.
Figure 3. NWMI LEU Test #1 133Xe for LEU (counts/300 seconds.
vs count #)Using the calibration determined response factor and the counts recorded during the LEUpurge, of 133Xe was collected from the LEU f l Using 133Xeproduction calculations from ORIGEN, and assays of dissolved LEUf solution, themeasured activity of the collected 133Xe represents of the Xe produced by theirradiation of the ý of LEUPage 4 of 4