WO1999063546A2 - Dispositif de stockage de radio-isotopes gazeux - Google Patents

Dispositif de stockage de radio-isotopes gazeux Download PDF

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Publication number
WO1999063546A2
WO1999063546A2 PCT/US1999/011514 US9911514W WO9963546A2 WO 1999063546 A2 WO1999063546 A2 WO 1999063546A2 US 9911514 W US9911514 W US 9911514W WO 9963546 A2 WO9963546 A2 WO 9963546A2
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WO
WIPO (PCT)
Prior art keywords
gaseous waste
waste
storage tank
gaseous
compressor
Prior art date
Application number
PCT/US1999/011514
Other languages
English (en)
Other versions
WO1999063546A3 (fr
Inventor
Eyal Mishani
Roland Chisin
Nachum Lifshits
Original Assignee
Hadasit Research Services & Development Company Ltd.
Friedman, Mark, M.
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Hadasit Research Services & Development Company Ltd., Friedman, Mark, M. filed Critical Hadasit Research Services & Development Company Ltd.
Priority to AU43125/99A priority Critical patent/AU4312599A/en
Publication of WO1999063546A2 publication Critical patent/WO1999063546A2/fr
Publication of WO1999063546A3 publication Critical patent/WO1999063546A3/fr

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/002—Containers for fluid radioactive wastes

Definitions

  • the present invention relates to a device for safely collecting and
  • radioisotopes in gaseous form until they can be safely released into
  • radioisotopes have sufficiently decayed to permit safe release.
  • radioactive waste containing long-lived radioisotopes such as
  • containers for storing these wastes must be able to contain the wastes for such a
  • the tightly sealed unit can be safely
  • radioisotopes used in medical applications such as PET
  • radioisotopes would be prohibitively expensive and inefficient, in addition to
  • radioisotopes for a short period of time is required, until the radioactive waste
  • the radioactive material is removed with an adsorbent material
  • PET radiopharmaceuticals have radioactive gaseous by-products which are
  • U.S. Patent No. 5,368,633 discloses a system for compressing
  • the first circuit is a recirculation line through a pressure control
  • a gas pump is
  • disposal unit for disposing of gaseous waste including at least one radioisotopic
  • the gas waste disposal unit comprising: (a) a storage tank for storing
  • the storage tank featuring: (i) an outlet valve for removing
  • Controller for controlling the compressor and for determining the pressure of
  • the storage tank further comprises: (iii) a substantially rigid
  • a general atmosphere is accessible through the outlet valve when the outlet
  • valve is open, such that the gaseous waste is removed from the storage tank by
  • valve is open. Most preferably, a pressure is present between the outer wall
  • the flexible inner membrane is substantially similar to the pressure between the
  • the gas waste disposal unit further comprises: (d) a detector
  • waste disposal unit further comprises a trap for trapping a substance in the
  • the trap is a liquid trap and the substance is moisture
  • the trap is a charcoal
  • the trap is a soda-lime trap.
  • At least one radioisotopic material includes a radioisotope with a short-life.
  • the radioisotope with the short-life is selected from the group consisting of:
  • the predetermined limit is a period of time.
  • the method further comprises the step of monitoring an activity
  • the predetermined limit is a preset level of
  • radioactivity such that when the activity of the radioisotope is substantially
  • the outlet valve includes the step of releasing the gaseous waste from the outlet
  • radioisotope the system for disposing of gaseous waste comprising: (a) a
  • radioisotope and for producing the gaseous waste including the at least one radioisotope and for producing the gaseous waste including the at least one radioisotope and for producing the gaseous waste including the at least one radioisotope and for producing the gaseous waste including the at least one radioisotope and for producing the gaseous waste including the at least one radioisotope and for producing the gaseous waste including the at least one radioisotope and for producing the gaseous waste including the at least one
  • radioisotope (c) a gas waste disposal unit for being connected to the
  • the gas waste disposal unit comprising: (i) a storage
  • the storage tank for storing the gaseous waste, the storage tank featuring: (1) an outlet
  • short half-life refers to a half-life of less than
  • FIG. 1 is a schematic diagram of an illustrative example of a gas waste
  • FIG. 2 is a schematic diagram of an illustrative example of a gas waste
  • FIGS. 3A-3C illustrate radioactivity produced and stored with the
  • the present invention is of a device for short-term storage of radioactive
  • radioactive gases containing short-lived radioisotopes.
  • the material can be any material that has decayed to a safe level.
  • the device of the present invention has the
  • radioactive material according to the present invention may be better
  • Figure 1 shows a schematic diagram of
  • a gas waste is a gas waste
  • Storage tank 12 preferably includes
  • a substantially rigid outer wall 14 constructed of a substance such as metal, and
  • 16 is preferably made from a polymeric substance such as plastic, more preferably a plastic which is relatively chemically inert.
  • storage tank 12 is that if flexible inner membrane 16
  • Such a type of storage tank 12 can be obtained from Oran Ltd. (Jerusalem,
  • the compressed air has a predetermined pressure of
  • membrane 16 expands, for example from a substantially completely collapsed
  • volume causes the pressure of the compressed air between outer wall 14 and
  • Storage tank 12 should be able to hold radioactive or other hazardous
  • gaseous waste for at least about 24 hours, more preferably for at least about one
  • waste is removed, for example by being released to the atmosphere.
  • the gaseous waste includes at least one radioisotopic material
  • radioisotope having a radioisotope with a short half-life, including but not limited to [F-18], [C- l 1], [N- 13], and [0- 15], so that the waste can be held in storage tank 12
  • tank 12 is more preferably substantially cylindrical in shape, and is most
  • storage tank 12 should be about 3 bar.
  • Storage tank 12 features an inlet valve 20, which is preferably a one-way
  • outlet valve 22 When outlet valve 22 is open, gases are able to
  • tank inlet tube 24 is made from a polymeric
  • the material more preferably a semi-rigid or rigid material. Most preferably, the
  • polymeric material is substantially chemically inert.
  • An example of a suitable polymeric material is substantially chemically inert.
  • polymeric material is P VC (polyvinyl chloride) plastic, although of course
  • Tank inlet tube 24 is connected to a compressor 26.
  • Compressor 26 is
  • compressor 26 preferably a 0.5 HP (horsepower) compressor. More preferably, compressor 26
  • compressor 26 can create a vacuum
  • Compressor 26 is preferably controlled by an Electrical Pressure
  • EPC 28 could be a type RT-121 compressor (Danfoss,
  • EPC 28 is capable of maintaining pressure
  • EPC 28 is in gaseous
  • EPC 28 is able
  • compressor inlet tube 30 for example by causing compressor 26 to become
  • a pressure gauge 34 may also be attached to
  • compressor inlet tube 30 for determining a pressure of the gas within
  • compressor inlet tube 30 Compressor inlet tube 30 and EPC tube 32 are both preferably made
  • the polymeric material is substantially chemically inert.
  • a suitable polymeric material is PVC (polyvinyl chloride) plastic
  • Compressor inlet tube 30 is preferably connected to at least one trap, of
  • Traps 36 are interconnected by a plurality of trap
  • plurality of traps 36 include a liquid trap 40 for trapping any
  • moisture within the gaseous waste for example in the form of liquid droplets.
  • plurality of traps 36 also include a soda-lime trap 42 and
  • gaseous waste enters at least one, and preferably a plurality
  • manifold outlet tube 48 features
  • a manifold pressure gauge 50 for determining the pressure of the material
  • Manifold 52 is connected to the chemistry waste valves
  • trap tubes 38 and manifold outlet tube 48 are made from a polymeric material, more preferably a
  • the polymeric material is
  • PVC polyvinyl chloride
  • unit 10 is preferably part of a gas waste system (shown in more detail in Figure
  • Radioactivity in storage tank 12 is preferably
  • monitor 56 which may be placed at a distance from storage tank
  • the radioisotopes for example after being stored to allow decay of the radioisotopes, the
  • the predetermined level is the amount of radioactivity considered to
  • outlet valve 22 could be allowed to escape to the general atmosphere through outlet valve 22.
  • gas waste disposal unit 10 The preferred operation of gas waste disposal unit 10 is as follows. Gas
  • waste disposal unit 10 is preferably connected to a PLC (programmable logic controller, not shown, see Figure 2 below) which automatically activates gas
  • gas waste disposal unit 10 is
  • activation and deactivation of gas waste disposal unit 10 is preferably
  • valve 20 of storage tank 12 is either opened upon activation of gas waste device
  • valve 46 is either opened upon
  • EPC 28 controls the pressure of the gas by activating
  • the gas pressure lies within a range of from
  • radiochemistry facility are opened to gas waste disposal unit 10 through
  • compressor 26 Without the requirement for such continuous use, compressor 26 may be relatively inexpensive, since a relatively less robust type
  • Figure 2 depicts an illustrative schematic preferred embodiment of an
  • a gas waste storage system 58 features three major
  • a cyclotron 60 at least one on-line radiation monitoring channel
  • Gas waste disposal unit 10 is substantially
  • Cyclotron 60 could be a 18 MeV negative ion (H ⁇ )
  • cyclotron 60 is connected to a radiochemistry facility 66 for
  • Each radiation monitoring channel 62 is preferably composed of at least
  • Detector 68 could be a GM-tube or a high sensitivity 2"x2"
  • the GM-tube could be a high
  • sensitivity GM-42 detector based on a ZP-1201 Geiger tube, Centronic, UK.
  • Detector 68 is preferably capable of detecting radioactivity of various types
  • alpha, beta and gamma radiation more preferably including alpha, beta and gamma radiation.
  • GM-tube detector was used for monitoring the radiation level in the gas waste
  • Radiopharmaceuticals are summarized in Table 1. High radiation levels were
  • waste system prevents the release in the atmosphere of radioactive by-products
  • Radiation levels in a cyclotron-radiochemistry facility were measured during the production of commonly used PET radiopharmaceuticals by a comprehensive computerized monitoring system.
  • the system consists of three major components : on-line radiation monitoring channels, an area control unit, and a gas waste management unit.
  • on-line radiation monitoring channels During production the radiation levels were measured in the cyclotron vault, inside automatic chemistry production and research shielded cells, in the radiochemistry room, in the gas waste decay tank, in the chimney filters, and at the top of the cells chimney.
  • Each detector was calibrated in a known radiation field, and a special detector dead time correction was performed in order to achieve detected signal-to-radiation linearity for the Geiger tubes located in the radiochemistry production and research cells.
  • PET Positron Emission Tomography
  • Radioisotopes were generated with a 18 MeV negative ion (H ⁇ ) cyclotron (Model 18/9, Ion Beam
  • [O-15]Water, [F-18]FDG were produced with IBA automated chemistry units.
  • [C-l l]deprenyl was produced with a Nuclear Interface automated chemistry unit (Nuclear Interface, Munster, Germany). Data was collected over a year during the production of each batch of [F- 18]FDG (50-800 mCi), [C-l l]Deprenyl (4-50 mCi), [O-15]Water (50-250 mCi), and [N-13]Ammonia (50-300 mCi).
  • the monitoring system consists of three major components : on-line radiation monitoring channels, an area control unit, and a gas waste management unit.
  • Each of the radiation monitoring channels is composed of a detector and a Data Processing Unit (DPU).
  • the DPU's are connected to one control PC with an analysis software.
  • the area control unit includes field sensors (pressure, humidity, doors position, etc.), a Programmable Logic Controller (PLC) and a Man Machine Interface (MMI) (scheme 1 ).
  • PLC Programmable Logic Controller
  • MMI Man Machine Interface
  • the system includes sixteen detectors, twelve are GM-tubes and four are high sensitivity 2"x2" Nal (Tl) scintillation detectors. Out of theses twelve GM-tubes three are high sensitivity GM-42 detectors (based on a ZP-1201 Geiger tubes, Centronic, UK) and are used for area monitoring in the radiochemistry lab and the basement area, and for monitoring the radiation levels in the gas waste tank (scheme 2).
  • GM-41 based on ZP-1313 Geiger tubes, Centronic, UK
  • Scheme 2 cyclotron vault
  • the scintillation detectors are located in the ventilation system (one at the chimney filters, two at the end of each chimney), and one is used to monitor the radiation levels in the liquid disposal tank (scheme 2).
  • Each type of detector has its own electronics circuit for providing the power and amplifying the signal. It also has its own identity frequency recorded on the DPU, allowing for simple and automatic system recognition of each type of detector. This frequency is produced by an internal oscillator and transferred to the DPU on one of the detectors leads.
  • each detector is calibrated by adjusting the frequency of the oscillator in a known radiation field in order to achieve accurate signal. This calibration factor is saved in the detector as a specific frequency for each detector, and is transferred to the DPU.
  • Equation 1 determines the conversion factor (F) between the detector pulse rate (in cps) and the activity concentration ( LiCi/m'). This factor is obtained from the probability of a photon generated on the surface of the duct to scintillate in the detector.
  • Each DPU consist of a microcontroller 80L32 (Intel, IL, USA), operation file programmed in EPROM-27C256 (Texas Inst., USA), and a display unit.
  • the microcontroller opens and closes the communication channels, commands the transmission, and the display unit driver.
  • the DPU performs the following functions: It provides the radiation levels monitored by each detector, alerts by audible and visual alarm in case of radiation levels exceeding a predetermined threshold or in case of detector failure, and communicates with the control station.
  • the DPU also calculates the calibration factor as the ratio of the detector specific frequency to the original detector type frequency, and the correct radiation field by multiplying the detected rate of pulses by the calibration factor (eq. 2).
  • the radiation levels are transferred from the DPU via a RS 485 communication network to the PC for on-line display and documentation.
  • Displayed radiation field count rate of pulsesxdeteclor specific frequency/original detector type frequency.
  • the gas waste system consists of an expansion tank, a compressor, an Electrical Pressure Controller (EPC), a liquid trap, a one way valve, and manifold and pressure gauges (scheme 3).
  • the compressor is a 0.5 HP and can develop an adjustable pressure up to 12 bars at the exit. It can create a vacuum of 0.1 bar and can work continuously up to two hours.
  • the EPC type RT-121, Danfoss, Denmark
  • the gas waste system is connected to the PLC which switches the system on and off whenever a radiochemical process is started or completed.
  • the pressure in the waste system is maintained by the EPC between 0.9 to 0.75 bars during operation in order to maintain a narrow range of pressure in the chemistry units when its valves are opened to the waste system, and in order to avoid continuous use of the compressor.
  • the choice of the adequate detector (ionization chamber, scintillator, Geiger or semi-conductor) for a specific task depends on the MDL needed (determined by radiation levels and background level), and on the detector life time.
  • the transmission of gamma rays is higher than the transmission of neutrons [8], therefore only one GM-tube was located in the cyclotron at a distance of 2 meters from the cyclotron.
  • GM tubes were placed in each of the strategic parts of the lab, and in the gas waste decay tank (expansion tank) (scheme 2).
  • sensitive scintillation probes were located in the ventilation deck and near the discharged liquid tank. The probes in the ventilation deck were placed inside the chimney near the filters, and outside the top of the chimney, in order to avoid absorption of radioactive particle on the detector surface.
  • Theoretical calculations and software simulation based on detector surrounding geometry and properties were made in order to convert the count rates obtained by the detector at the top of the chimney into activity concentration levels. The conversion factor that was obtained by software simulation
  • the gas waste system prevents the release in the atmosphere of radioactive by-products generated during radiopharmaceuticals production and of volatile compounds of failed radiochemistry processes.
  • the design of the gas waste tank increases the safety in the site and minimizes the space needed for such a system in comparison with traditional solutions such as large size ballons.
  • Radiation levels measured inside the vault were related to cyclotron operation.
  • a constant radiation level of 147 mR hr was observed in the vault at a distance of 2 meters from the cyclotron (scheme 5).
  • the beam current was decreased to 13 ⁇ A the radiation level decreased to 88 mR/hr.
  • [F-18]FDG under normal operation of the cyclotron with full target and constant beam current on target, a constant radiation level was observed in the cyclotron vault (scheme 4). This value changed when bombardment was performed on an empty target. The radiation level observed in the vault was also used for fine tuning of the beam.
  • the radiation level in the vault decreased to 1 -2 mR after 2 minutes. Unsuccessful or non-completed transfer will cause higher radiation levels and will be detected by the monitoring channel in the vault.
  • the monitoring channel in the water recovery unit (scheme 6), enables, after calibration, quantification of the activity at the begining of the synthesis and the calculation of the yield of [F- 18]fluoride production. In addition, the yield of the FDG production process can be easily calculated.
  • the follow up of radiation levels in the FDG hot cell is shown in scheme 7. Although we used only one monitoring channel it was sufficient, as shown in this graph, to identify transfers of the activity from the first reactor of the chemical unit to the second and to the purification columns. In addition loss of activity as volatile byproducts during evaporation steps was also observed by this monitoring channel and by the monitoring channel located at the shielded cell chimney filter.
  • This new monitoring system provides an effective solution for the control of various aspects of production and radiation safety in a cyclotron-radiochemistry facility.
  • the combination of a gas waste decay system and computerized monitoring channels located near each strategic point of the site allows for a comprehensive evaluation of radiochemical processes. Since signal to radiation level linearity was achieved for Geiger tubes and each monitoring channel calibrated, the results obtained can be used to quantify the yield of each step during the various radiosyntheses.
  • the gas waste unit permits to meet the radiation safety recommendations published by the IAEA.
  • the design of the gas waste tank increases the safety in the site, minimizes the space needed for a gas waste system (in comparison with traditional solution such as large size balloons) and provides longer time for decay.
  • Scheme 1 Monitoring system layout.
  • the detector was located outside the top of the chimney.
  • the beam current was reduced from 20 to 13 ⁇ Am.
  • A radiation level in the gas waste tank
  • B radiation level in the chemistry cell. [0-15] was produced in batches providing approximately 250mCi of final product for each batch.
  • A loss of activity during the second and third steps
  • 9B loss of activity during the trapping step, and improvment in the third and second step
  • 9C "optimal" n.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Measurement Of Radiation (AREA)
  • Nuclear Medicine (AREA)

Abstract

La présente invention concerne un système d'élimination de déchets gazeux renfermant au moins un matériau radio-isotopique contenant au moins un radio-isotope. Ce système d'élimination de déchets gazeux est constitué, d'une part (a) d'un cyclotron destiné à la production d'au moins un radio-isotope, et d'autre part (b) d'un laboratoire de radiochimie permettant la production, non seulement du matériau radio-isotopique contenant le radio-isotope considéré, mais également du déchet gazeux contenant le radio-isotope considéré. Le système comporte en outre (c) une unité d'élimination des déchets gazeux pouvant se raccorder au laboratoire de radiochimie et capable de recevoir les déchets gazeux en provenance du laboratoire de radiochimie. Cette unité d'élimination des déchets gazeux comprend (i) un réservoir de stockage, (ii) un compresseur, et (iii) un régulateur électrique de pression. Le réservoir de stockage (i), qui sert au stockage des déchets gazeux, est pourvu, d'une part (1) d'une soupape d'échappement servant à évacuer les déchets gazeux du réservoir de stockage, et d'autre part (2) d'une soupape d'admission permettant aux déchets gazeux de pénétrer dans le réservoir de stockage. Le compresseur (ii) est branché sur la soupape d'admission de façon à pressuriser les déchets gazeux dans le réservoir de stockage conférant ainsi de la pression aux déchets gazeux radioactifs. Le régulateur électrique de pression (iii) sert à commander le compresseur et à déterminer la pression des déchets gazeux de façon que le compresseur soit activé par intermittence par le régulateur maintenant ainsi la pression des déchets gazeux dans le réservoir de stockage.
PCT/US1999/011514 1998-05-29 1999-05-26 Dispositif de stockage de radio-isotopes gazeux WO1999063546A2 (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
AU43125/99A AU4312599A (en) 1998-05-29 1999-05-26 Device for storage of gaseous radioisotopes

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US8648298A 1998-05-29 1998-05-29
US09/086,482 1998-05-29

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Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP2800627A4 (fr) * 2012-01-05 2015-08-19 Bencar Ab Système de contrôle de l'environnement dans une boîte de réaction
WO2020112984A1 (fr) * 2018-11-30 2020-06-04 Dana-Farber Cancer Institute, Inc. Dispositif de suppression de son pour système de capture de gaz de produit cyclotron
KR102186485B1 (ko) * 2020-04-16 2020-12-03 케이비엔지니어링(주) 방사성 물질 저감 장치
EP3385759B1 (fr) * 2017-04-07 2021-07-14 Comecer Netherlands B.V. Système de surveillance réelle de la libération de particules radioactives, installation de construction équipée de celui-ci et procédé associé

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US3963460A (en) * 1973-04-04 1976-06-15 Licentia Patent-Verwaltungs-G.M.B.H. Method and apparatus for treating waste gases containing radioactive impurities, particularly krypton and xenon nuclides
US4277361A (en) * 1977-05-04 1981-07-07 Atlantic Richfield Company Ventilating system for reprocessing of nuclear fuel rods
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US4473529A (en) * 1980-05-23 1984-09-25 Framatome Device for collecting purge liquids and gases in an installation containing substances which may possess a certain degree of radioactivity
CH674671A5 (en) * 1988-07-20 1990-06-29 Vincenzo Pecorelli Liq. circulating gas compressor - uses electrical control unit to operate valves for liq. tank and check valve between gas and liq. tanks
US5332547A (en) * 1991-04-16 1994-07-26 Prolong Systems, Inc. Controlled atmosphere storage container
US5368633A (en) * 1993-08-12 1994-11-29 Morrison-Knudson (An Idaho Corporation) Pressurized radioactive gas treatment system

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP2800627A4 (fr) * 2012-01-05 2015-08-19 Bencar Ab Système de contrôle de l'environnement dans une boîte de réaction
US10074450B2 (en) 2012-01-05 2018-09-11 P M B, Sas System for controlling environment in a reaction box
EP3385759B1 (fr) * 2017-04-07 2021-07-14 Comecer Netherlands B.V. Système de surveillance réelle de la libération de particules radioactives, installation de construction équipée de celui-ci et procédé associé
WO2020112984A1 (fr) * 2018-11-30 2020-06-04 Dana-Farber Cancer Institute, Inc. Dispositif de suppression de son pour système de capture de gaz de produit cyclotron
EP3886712A4 (fr) * 2018-11-30 2022-11-09 Dana-Farber Cancer Institute, Inc. Dispositif de suppression de son pour système de capture de gaz de produit cyclotron
KR102186485B1 (ko) * 2020-04-16 2020-12-03 케이비엔지니어링(주) 방사성 물질 저감 장치

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WO1999063546A3 (fr) 2001-01-11
AU4312599A (en) 1999-12-20

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