Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.031 seconds
AbstractAbstract
[en] The widespread use of high intensity radiation sources, reactors and nuclear power plants requires the use of accident dose meters. An aluminium oxide ceramic dose meter has been developed. Because of its low atomic number and its small dimensions, it is suitable for dosimetry of gamma and mixed gamma-neutron radiation fields. The Al2O3 dose meter (diameter 6mm, thickness 1mm), containing Mg and Y activators gives a linear response between 1 and 2x105 rads. The peak in the emission spectrum of the Al203 dose meters constructed by us is near to 4400A. Two peaks can be observed on the glow curve at 250 and 2900C. The low temperature peak is not significant. The reproducibility of dose meters is within +-10%. Fading is less than 10% at room temperature for 24 hours, and not higher than 20% in 240 hours. The dose meters are suitable for repeated use provided they are annealed before use at 6000C for 2 hours. (author)
Source
International Atomic Energy Agency, Vienna (Austria); Nuclear Energy Agency, 75 - Paris (France); Proceedings series; p. 493-498; ISBN 92-0-020077-X; ; 1977; p. 493-498; IAEA; Vienna; Symposium on the handling of radiation accidents; Vienna, Austria; 28 Feb - 4 Mar 1977; IAEA-SM--215/45
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue