US3729631A
Expired / Lapsed
US
⏱️ 0.0 years remaining
Method and apparatus for the measurement of mixed gamma-neutron radiation dose equivalent
Assignee: Individual
•
Filing: 1970-05-22
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Granted: 1973-04-24
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Expires: 1990-05-22
Abstract
Abstract A method and apparatus for measuring mixed gamma-neutron dose equivalent by determining a current difference between the output of an ionization chamber and a scintillator which latter preferably comprises an organic compound and has a photomultiplier tube operatively connected therewith.
Inventors
- 👤 S Pszona
Bibliographic Details
Application Number
—
Jurisdiction
US
Data Source
google_patents
Last Synchronized
2026-10-30 00:54
CPC Classifications
G; G01; G01T; G01T3/00; G01T1/00; G01T1/02; G01T1/16; G01T1/20
Claims Analysis
Total Claims: 6
Claim 1
Independent Claim
116 words
Apparatus for measuring a mixed gamma-neutron dose equivalent comprising: a. an ionization chamber constructed of a tissue equivalent material and having an output means; b. a scintillation detector, said scintillation detector being made out of organic material aNd said scintillation detector being mounted in said ionization chamber; c. a photomultiplier tube in operative relation to said scintillation detector and having output means; d. and means for measuring the difference of outputs from said photomultiplier tube and said ionization chamber whereby said measured difference is utilized to provide a measure of the dose equivalent rate due to the linear relationship between the ratio of the scintillation counter current to the ionization chamber current and the quality factor.
Claim 2
Dependent Claim
116 words
Apparatus for measuring a mixed gamma-neutron dose equivalent comprising: a. an ionization chamber constructed of a tissue equivalent material and having an output means; b. a scintillation detector, said scintillation detector being made out of organic material aNd said scintillation detector being mounted in said ionization chamber; c. a photomultiplier tube in operative relation to said scintillation detector and having output means; d. and means for measuring the difference of outputs from said photomultiplier tube and said ionization chamber whereby said measured difference is utilized to provide a measure of the dose equivalent rate due to the linear relationship between the ratio of the scintillation counter current to the ionization chamber current and the quality factor.
Claim 3
Dependent Claim
116 words
Apparatus for measuring a mixed gamma-neutron dose equivalent comprising: a. an ionization chamber; b. a scintillation detector in said ionization chamber; c. a photomultiplier tube in operative relation to said scintillation detector and having output means; d. and means for measuring the difference of outputs from said photomultiplier tube and said ionization chamber, said means comprising a first and second resistor connected in series, said first resistor having one of its ends connected to the output of said ionization chamber and its other end connected to said output means of said photomultiplier tube whereby the linear relation between the scintillation counter current and the ionization chamber is utilized to provide a measure of dose equivalent rate.
Claim 4
Dependent Claim
116 words
Apparatus for measuring a mixed gamma-neutron dose equivalent comprising: a. an ionization chamber; b. a scintillation detector in said ionization chamber; c. a photomultiplier tube in operative relation to said scintillation detector and having output means; d. and means for measuring the difference of outputs from said photomultiplier tube and said ionization chamber, said means comprising a first and second resistor connected in series, said first resistor having one of its ends connected to the output of said ionization chamber and its other end connected to said output means of said photomultiplier tube whereby the linear relation between the scintillation counter current and the ionization chamber is utilized to provide a measure of dose equivalent rate.
Claim 5
Independent Claim
46 words
A method of measuring the dose equivalent in a mixed gamma-neutron radiation environment comprising; a. generating an output proportional to the absorbed dose rate of radiation; b. generating an output linearly proportional to the quality factor of radiation, and c. measuring the difference between said outputs.
Claim 6
Independent Claim
46 words
A method of measuring the dose equivalent in a mixed gamma-neutron radiation environment comprising; a. generating an output proportional to the absorbed dose rate of radiation; b. generating an output linearly proportional to the quality factor of radiation, and c. measuring the difference between said outputs.
References Cited (Backward Citations)
US3290500A
Cited
US3566118A
Cited
USPTO Annuity & Maintenance Windows
| Annuity Stage | Window Opens | Payment Deadline | Surcharge Period Until | Estimated Fee | Status |
|---|---|---|---|---|---|
| 3.5 Years (Year 4) | 1976-04-23 | 1976-10-23 | 1977-04-24 | $2000.00 | Window Closed / Lapsed |
| 7.5 Years (Year 8) | 1980-04-23 | 1980-10-23 | 1981-04-24 | $3760.00 | Window Closed / Lapsed |
| 11.5 Years (Year 12) | 1984-04-23 | 1984-10-23 | 1985-04-24 | $7700.00 | Window Closed / Lapsed |