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I-125
I wish to thank everyone who responded to my request for information
on source jigs for calibrating ion chambers.
I have another series of questions which revolve around the use and
detection of I-125.
We are currently beginning to use I-125 as a radiotracer in studies.
Most of the bugs are worked out for the use portion of the study. The
only problem that we are having is with detection.
Our license bounds us to reach an LLD of 300 dpm. This 300 dpm limit
is for fixed contamination. That is, we can't release items or
materials which contain fixed contamination greater than 300 dpm. The
source for this limit being Reg Guide 1.86 and Policy and Guidance
Directive FC 83-23," Termination of Byproduct, Source and Special
Nuclear Materials Licenses." Decay in storage is currently not an
option at our facility.
Can anyone tell me where the 300 dpm limit for releasing of I-125
contaminated material came from, or the basis for this limit? It seems
I-125 and I-129 require the same release limit as Ra-226, Ra-228,
Th-230, Th-228, Pa231, and Ac-227. Other isotopes from Iodine have a
significantly higher release limit.
We currently have a LEG-1 (Low Energy Gamma detector) calibrated to
I-129 which sees the 300 dpm, but only when static readings are taken.
I am under the impression that GM detectors such as the Ludlum Model 3
with a pancake probe will see the I-125 conversion electrons, but not
at the required LLD. I can't calibrate the Ludlums with I-129 because
the detector can't see the gammas.
The I-129 source which I ordered to calibrate the LEG-1 detector,
ESP-2 instrument was NIST traceable to 377 Bq. That is the actual
activity amount of I-129 was 377 Bq. This however, was placed in a
plastic backing and cover and sealed. The plastic backing was 2.7 mm.
When we tried to calibrate the instrument we were not seeing 377 Bq
because of attenuation of the low energy gammas through the plastic.
The source manufacturer stated he could not tell us the emission rate
of the source, only the actual activity of the material. He also
stated, the plastic could attenuate up to 10 % of the gammas but not
to hold him to that. We did our own attenuation experiments and got
attenuation of up to 50 %, but this was after emission through the
plastic. Based on this we assumed a 10% attenuation.
Does this seem reasonable ? Has anyone else run into this problem?
The next issue we had to tackle was the actual emission spectrum of
the I-129 source. Apparently, the source emits low energy gammas with
an intensity of around around 79%. I know the beta emission intensity
is 100%. I'm not sure what the other 21% emission entails.
Can anyone tell me what the other 21% is?
We now have a need for obtaining a backup instrument and detector for
researcher and radiation safety use. Instead of purchasing another LEG
we are trying to lease one. Does anyone know where I could lease an
LEG detector or equivalent? I have tried GTS but they have no
detectors which will meet the required LLD?
I apologize for the length of this message, but I believe these are
valid questions to ask and my resources are limited except for this
medium. Thank you for your patience. Please respond to my E-Mail
unless you feel the information can be used by other RADSAFE users.
Larry R. Sanders.
Radiation Technical Support
Battelle Memorial Institute
Larry_R_Sanders_at_~BMI4@battelle.org