Systems and methods for assaying a radioactive gas, and related scintillation cells

Patent metadata

Field	Value
Publication number	US-2018329077-A1
Application number	US-201715590359-A
Country	US
Kind code	A1
Filing date	May 9, 2017
Priority date	May 9, 2017
Publication date	Nov 15, 2018
Grant date	—

Abstract

A radioactive gas assay system comprises a scintillation cell production assembly, a detector assembly, a computer assembly, and a scintillation cell destruction assembly. The scintillation cell production assembly is configured to produce a scintillation cell comprising a glass scintillator shell containing a volume of radioactive gas. The detector assembly is configured to receive the scintillation cell and to detect photons emitted thereby. The computer assembly is configured to receive data from the detector assembly to automatically calculate an absolute activity of the volume of radioactive gas of the scintillation cell and radiation detection efficiencies of the detector assembly. The scintillation cell destruction assembly is configured to receive the scintillation cell and to rupture the substantially non-porous glass scintillator shell to release the volume of radioactive gas. A method of assaying a radioactive gas, and a scintillation cell are also described.

First claim

What is claimed is:

1 . A radioactive gas assay system, comprising:
a scintillation cell production assembly configured to produce a scintillation cell comprising a glass scintillator shell containing a volume of radioactive gas; a detector assembly configured to receive the scintillation cell and to detect photons emitted by the scintillation cell; a computer assembly operatively associated with and configured to receive data from the detector assembly to automatically calculate an absolute activity of the volume of radioactive gas of the scintillation cell as well as radiation detection efficiencies of the detector assembly; and a scintillation cell destruction assembly configured to receive the scintillation cell and to rupture the glass scintillator shell thereof to release the volume of radioactive gas contained therein.

2 . The radioactive gas assay system of claim 1 , wherein the scintillation cell production assembly comprises:
a retention device configured to receive and hold a preliminary glass scintillator structure; a gas delivery device configured to connect to the preliminary glass scintillator structure and to deliver radioactive gas into a cavity in the preliminary glass scintillator structure to form a gas-filled preliminary glass scintillator structure; and a sealing device configured and positioned to seal and separate a portion of the gas-filled preliminary glass scintillator structure to form the scintillation cell.

3 . The radioactive gas assay system of claim 1 , wherein the scintillation cell production assembly is configured to form the glass scintillator shell of the scintillation cell from a glass scintillator material formulated to completely contain the volume of radioactive gas and to substantially prevent transmission of beta radiation therethrough while substantially permitting photon emission from the scintillation cell.

4 . The radioactive gas assay system of claim 1 , wherein the detector assembly comprises:
a gamma ray well detector configured to receive and removably hold the scintillation cell in an opening therein and to detect gamma photons emitted from the scintillation cell; and a light sensor configured to at least partially extend into the opening in the gamma ray well detector and to detect scintillation photons emitted from the scintillation cell.

5 . The radioactive gas assay system of claim 4 , wherein the gamma ray well detector comprises a high-purity germanium well detector, and wherein the light sensor comprises a photomultiplier tube.

6 . The radioactive gas assay system of claim 4 , wherein the computer assembly is configured to receive gamma photon counts from the gamma ray well detector and scintillation photon counts from the light sensor, and to automatically calculate the absolute activity of the volume of radioactive gas of the scintillation cell, a beta detection efficiency of the detector assembly, and a gamma detection efficiency of the detector assembly at least partially based on the received gamma photon counts and the received scintillation photon counts.

7 . The radioactive gas assay system of claim 1 , wherein the scintillation cell destruction assembly comprises:
a containment vessel configured to receive and hold the scintillation cell; and a device configured and positioned to rupture the glass scintillator shell of the scintillation cell to release the volume of radioactive gas contained therein.

8 . The radioactive gas assay system of claim 1 , further comprising a radiative gas source in fluid communication with the scintillation cell production assembly, the radiative gas source configured to hold a radioactive gas comprising one or more of 127 Xe, 131m Xe, 133 Xe, 133m Xe, and 135 Xe and to direct the radioactive gas to the scintillation cell production assembly.

9 . The radioactive gas assay system of claim 8 , further comprising a manifold configured and positioned to direct the volume of radioactive gas released from the scintillation cell by the scintillation cell destruction assembly into one or more of the radiative gas source and the scintillation cell production assembly.

10 . A method of assaying a radioactive gas, comprising:
forming a scintillation cell comprising a substantially non-porous glass scintillator shell containing a volume of radioactive gas; delivering the scintillation cell into a detector assembly comprising a gamma well detector and a light sensor to detect photons emitted from the scintillation cell; calculating an absolute activity of the volume of radioactive gas of the scintillation cell and radiation detection efficiencies of the detector assembly using a computer assembly in communication with the detector assembly; and removing the scintillation cell from the detector assembly.

11 . The method of claim 10 , wherein forming a scintillation cell comprises:
delivering a radioactive gas comprising one or more radioxenon isotopes into a preliminary glass scintillator structure comprising a substantially non-porous glass scintillator material to form a gas-filled preliminary glass scintillator structure; and sealing and separating a portion of the gas-filled preliminary glass scintillator structure.

12 . The method of claim 11 , further comprising:
selecting the radioactive gas to comprise one or more of 127 Xe, 131m Xe, 133 Xe, 133m Xe, and 135 Xe; and selecting the substantially non-porous glass scintillator material to comprise a cerium activated lithium silicate glass scintillator having a density within a range of from about 2.40 g/cm 3 to about 2.65 g/cm 3 .

13 . The method of claim 10 , wherein delivering the scintillation cell into a detector assembly comprises:
delivering the scintillation cell into an opening in the gamma well detector, the scintillation cell remaining substantially unattached to surfaces of the gamma well detector within the opening; and inserting the light sensor into the opening in the gamma well detector to overlie the scintillation cell within the opening.

14 . The method of claim 10 , wherein delivering the scintillation cell into a detector assembly comprising a gamma well detector and a light sensor to detect photons emitted from the scintillation cell comprises:
selecting the gamma well detector to comprise a high-purity germanium well detector; selecting the light sensor to comprise a photomultiplier tube; detecting and counting gamma photons emitted from the scintillation cell using the high-purity germanium well detector; and detecting and counting scintillation photons emitted from the scintillation cell using the photomultiplier tube.

15 . The method of claim 14 , wherein calculating an absolute activity of the volume of radioactive gas of the scintillation cell and radiation detection efficiencies of the detector assembly comprises automatically calculating the absolute activity of the volume of radioactive gas of the scintillation cell, a beta detection efficiency of the detector assembly, and a gamma detection efficiency of the detector assembly using the computer assembly at least partially based on gamma photon counts and scintillation photon counts received from the high-purity germanium well detector and the photomultiplier tube.

16 . The method of claim 10 , further comprising:
rupturing the substantially non-porous glass scintillator shell of the scintillation cell after removing the scintillation cell from the detector assembly to release the volume of radioactive gas contained within the substantially non-porous glass scintillator shell; and recovering at least a portio

Assignees

• Battelle Energy Alliance Llc
• Battelle Memorial Institute

Inventors

• Robinson Troy A
• Finck Martha R
• Cooper Matthew W
• Hayes James C
• Reber Edward L

Classifications

• G21F9/008

  Apparatus specially adapted for mixing or disposing radioactively contamined material (G21F9/305 and G21F9/308 take precedence) · CPC title

• G01T7/02

  Collecting means for receiving or storing samples to be investigated {and possibly directly transporting the samples to the measuring arrangement; particularly for investigating radioactive fluids (sampling, preparing specimens for investigation in general G01N1/00, G01N1/02; shielded cells or rooms structurally combined with manipulatin devices G21F; measuring of chromatographically separated samples G01N30/00 - G01N30/96)} · CPC title

• G01N21/766

  of gases · CPC title

• G01T1/1663

  Processing methods of scan data, e.g. involving contrast enhancement, background reduction, smoothing, motion correction, dual radio-isotope scanning, computer processing (for measuring spatial distribution of radiation G01T1/2992; general purpose image data processing G06T1/00; computerized tomography G06T12/00); Ancillary equipment · CPC title

• G01T1/20

  with scintillation detectors · CPC title