Patent US4092541A successfully refreshed from Google Patents.
US4092541A
Expired / Lapsed
US
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Method for determining the activity concentration in waste gases for specific nuclides
Assignee: Kraftwerk Union AG
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Filing: 1976-08-12
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Granted: 1978-05-30
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Expires: 1996-08-12
Abstract
Abstract Method of determining the activity concentration of the radio nuclides in waste gases of nuclear power plants by bleeding a part of the gas stream, compressing it to a high superatmospheric pressure, passing the compressed gas into a high pressure chamber where the specific nuclides are measured by means of a calibrated Ge (Li) detector, and returning the gas from the chamber at reduced pressure to the gas stream. The activity concentration of the gas in the high-pressure vessel permits measurement of the specific nuclides, and also permits detection of waste gas activities which are below the customary detection limits.
Inventors
- 👤 Herbert Neidl
Bibliographic Details
Application Number
—
Jurisdiction
US
Data Source
google_patents
Last Synchronized
2026-10-30 14:10
CPC Classifications
G; G01; G01T; G01T7/00; G01T7/02; G21; G21C; G21C17/00; Y; Y02; Y02E; Y02E30/00; Y02E30/30
Claims Analysis
Total Claims: 8
Claim 1
Independent Claim
138 words
In a method for determining the activity concentration of the radionuclides contained in gas stream, particularly in waste gases of nuclear power plants, by means of gamma spectroscopy, the improvement comprising bleeding part of the gas stream, compressing said gas stream to a high superatmospheric pressure, conducting said gas stream at a high superatmospheric pressure into a high-pressure vessel, measuring said gas in said high-pressure vessel in the state of high superatmospheric pressure for specific nuclides by means of a calibrated Ge(Li) detector, wherein the activity concentrations of the individual nuclides are measured and evaluated by a pulse amplitude analyzer connected to said Ge(Li) detector as well as a computer connected to said pulse amplitude analyzer, and discharging said gas from said high-pressure vessel, and returning said discharge gas to the gas stream from which it was bled.
Claim 2
Dependent Claim
138 words
In a method for determining the activity concentration of the radionuclides contained in gas stream, particularly in waste gases of nuclear power plants, by means of gamma spectroscopy, the improvement comprising bleeding part of the gas stream, compressing said gas stream to a high superatmospheric pressure, conducting said gas stream at a high superatmospheric pressure into a high-pressure vessel, measuring said gas in said high-pressure vessel in the state of high superatmospheric pressure for specific nuclides by means of a calibrated Ge(Li) detector, wherein the activity concentrations of the individual nuclides are measured and evaluated by a pulse amplitude analyzer connected to said Ge(Li) detector as well as a computer connected to said pulse amplitude analyzer, and discharging said gas from said high-pressure vessel, and returning said discharge gas to the gas stream from which it was bled.
Claim 3
Dependent Claim
22 words
Method according to claim 1, wherein said gas stream flows through an aerosol and an iodine filter before compressing said gas stream.
Claim 4
Dependent Claim
37 words
Method according to claim 1, wherein said gas stream is continuously fed into said high-pressure vessel and continuously discharged from said high-pressure vessel, and a state of high superatmospheric pressure is continously maintained in said high-pressure vessel.
Claim 5
Dependent Claim
48 words
Method according to claim 1, wherein said gas stream is intermittantly fed into said high-pressure vessel without discharge of gas therefrom to provide gas in a state of high superatmospheric pressure in said high-pressure vessel for measurement, and the gas after measurement is discharged from said high-pressure vessel.
Claim 6
Dependent Claim
25 words
Method according to claim 1, wherein said gas in said high-pressure vessel for measuring is at a pressure of between about 100 to 300 bar.
Claim 7
Dependent Claim
204 words
In a method for determining the activity concentration of the radionuclides contained in gas stream, particularly in waste gases of nuclear power plants, by means of gamma spectroscopy, the improvement comprising bleeding part of the gas stream, compressing said gas stream to a high superatmospheric pressure, conducting said gas stream at a high superatmospheric pressure into a high-pressure vessel, measuring said gas in said high-pressure vessel in the state of high superatmospheric pressure for specific nuclides by means of a Ge(Li) detector calibrated by the following steps: (a) taking a certain volume of coolant from the reactor cooling loop of a nuclear reactor; (b) determining the activity concentration of fission gases in this volume of coolant for specific nuclides; (c) degassing this volume of coolant; (d) transferring the amount of gas obtained by degassing into said high-pressure vessel; (e) determining the activity concentration remaining in the coolant volume in comparison with b), whereby the activity concentration in the high-pressure vessel of the individual fission gas nuclides is obtained; and (f) calibrating the measuring apparatus by means of the activity concentrations known from e), discharging said gas from said high-pressure vessel, and returning said discharged gas to the gas stream from which it was bled.
Claim 8
Dependent Claim
204 words
In a method for determining the activity concentration of the radionuclides contained in gas stream, particularly in waste gases of nuclear power plants, by means of gamma spectroscopy, the improvement comprising bleeding part of the gas stream, compressing said gas stream to a high superatmospheric pressure, conducting said gas stream at a high superatmospheric pressure into a high-pressure vessel, measuring said gas in said high-pressure vessel in the state of high superatmospheric pressure for specific nuclides by means of a Ge(Li) detector calibrated by the following steps: (a) taking a certain volume of coolant from the reactor cooling loop of a nuclear reactor; (b) determining the activity concentration of fission gases in this volume of coolant for specific nuclides; (c) degassing this volume of coolant; (d) transferring the amount of gas obtained by degassing into said high-pressure vessel; (e) determining the activity concentration remaining in the coolant volume in comparison with b), whereby the activity concentration in the high-pressure vessel of the individual fission gas nuclides is obtained; and (f) calibrating the measuring apparatus by means of the activity concentrations known from e), discharging said gas from said high-pressure vessel, and returning said discharged gas to the gas stream from which it was bled.
References Cited (Backward Citations)
USPTO Annuity & Maintenance Windows
| Annuity Stage | Window Opens | Payment Deadline | Surcharge Period Until | Estimated Fee | Status |
|---|---|---|---|---|---|
| 3.5 Years (Year 4) | 1981-05-29 | 1981-11-28 | 1982-05-30 | $2000.00 | Window Closed / Lapsed |
| 7.5 Years (Year 8) | 1985-05-29 | 1985-11-28 | 1986-05-30 | $3760.00 | Window Closed / Lapsed |
| 11.5 Years (Year 12) | 1989-05-29 | 1989-11-28 | 1990-05-30 | $7700.00 | Window Closed / Lapsed |