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Title: PERSONNEL DOSIMETER

Abstract

A personnel dosimeter sensitive to both gamma and beta radiation is described. The dosimeter consists of an electrical conductive cylinder having a wall thickness of substantially 7 milligrams per square centimeter and an electrode disposed axially within the cylinder and insulated therefrom to maintain a potential impressed between the electrode and the cylinder. A cylindrical perforated shield provided with a known percentage of void area is disposed concentrically about the cylinder. The shield is formed of a material which does not contain more than 15 percent of an element higher than atomic weight 13. The dose actually received is at most the gamma dose plus the beta dose indicated by discharge of the dosimeter divided by the known percentage.

Inventors:
; ;
Issue Date:
OSTI Identifier:
4239934
Patent Number(s):
2875343
Assignee:
U.S. Atomic Energy Commission
Patent Classifications (CPCs):
H - ELECTRICITY H01 - BASIC ELECTRIC ELEMENTS H01J - ELECTRIC DISCHARGE TUBES OR DISCHARGE LAMPS
NSA Number:
NSA-13-015333
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-59
Country of Publication:
United States
Language:
English
Subject:
INSTRUMENTS; BETA DETECTION; CONFIGURATION; DIELECTRICS; DOSEMETERS; ELECTRIC CHARGES; ELECTRIC DISCHARGES; ELECTRIC POTENTIAL; ELECTRODES; ELEMENTS; GAMMA DETECTION; PERSONNEL; PLANNING; RADIATION DOSES; SHIELDING

Citation Formats

Birkhoff, R D, Hubbell, Jr, H H, and Johnson, R M. PERSONNEL DOSIMETER. United States: N. p., 1959. Web.
Birkhoff, R D, Hubbell, Jr, H H, & Johnson, R M. PERSONNEL DOSIMETER. United States.
Birkhoff, R D, Hubbell, Jr, H H, and Johnson, R M. Tue . "PERSONNEL DOSIMETER". United States.
@article{osti_4239934,
title = {PERSONNEL DOSIMETER},
author = {Birkhoff, R D and Hubbell, Jr, H H and Johnson, R M},
abstractNote = {A personnel dosimeter sensitive to both gamma and beta radiation is described. The dosimeter consists of an electrical conductive cylinder having a wall thickness of substantially 7 milligrams per square centimeter and an electrode disposed axially within the cylinder and insulated therefrom to maintain a potential impressed between the electrode and the cylinder. A cylindrical perforated shield provided with a known percentage of void area is disposed concentrically about the cylinder. The shield is formed of a material which does not contain more than 15 percent of an element higher than atomic weight 13. The dose actually received is at most the gamma dose plus the beta dose indicated by discharge of the dosimeter divided by the known percentage.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {2}
}