ORNL-4191 - the Molten Salt Energy Technologies Web Site
ORNL-4191 - the Molten Salt Energy Technologies Web Site
ORNL-4191 - the Molten Salt Energy Technologies Web Site
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c<br />
41<br />
Table 2.1. Radiation Levels Following Steps in Decontamination of an MSRE Sampler-Enricher Manipulator Hand<br />
_____I____<br />
Cleaning Radiation Level<br />
Cleaning Treatment Time Ntri Treatment<br />
None (as received)<br />
Detergent (Duz) jet Spray<br />
Rinse (water)<br />
Detergent (Duz) jet spray<br />
Formula 50<br />
Dilute HNO,<br />
Bolt freeing solvent with acetone tinse<br />
Concentrated HNO,<br />
Scrub with scouring powder (&IB-O)~<br />
Scrub with scouring powder (BaB-0)<br />
Formula 50<br />
Concentrated HNO,<br />
Scrub with scouring powder (Ran-0)<br />
Clean with concentrated HNO,<br />
Acetone rinse<br />
smears '<br />
aRemoved to laboratory hood.<br />
bZirconium and rutlienium.<br />
CIn disintegrations per minute.<br />
system and in planning for maintenance of <strong>the</strong><br />
components. On <strong>the</strong> basis of <strong>the</strong>se needs, a study<br />
of possibly useful devices was started.<br />
The concept of <strong>the</strong> pinhole camera using radiation<br />
shielding and gamma-ray-sensitive film was<br />
evaluated dong with a system using a portable<br />
collimator and a small gamma-sensitive dosimeter.<br />
It was determined that while <strong>the</strong> camera method<br />
was feasible, <strong>the</strong> results to date did not provide<br />
very good resolution of position, intensity, and<br />
size. The problem of calibration of <strong>the</strong> film for<br />
use in radiation fields of unknown energy appeared<br />
difficult. However, <strong>the</strong> time required to survey an<br />
area would be short, approximately Equal to <strong>the</strong><br />
required exposure time for <strong>the</strong> film. The use of<br />
<strong>the</strong> collimator method would take longer to complete<br />
a survey, but possibly could yield better<br />
resolution. This method also offered <strong>the</strong> potential<br />
of giving information on <strong>the</strong> gamma-ray energy<br />
spectrum of <strong>the</strong> source. A series of experiments<br />
with <strong>the</strong> collimator was conducted to evaluate <strong>the</strong><br />
method, with <strong>the</strong> results described below.<br />
(min) (r/hr)<br />
5<br />
5<br />
10<br />
10<br />
5<br />
10<br />
5<br />
5<br />
5<br />
5<br />
5<br />
5<br />
5<br />
300<br />
100<br />
75<br />
25<br />
7.5<br />
5.0<br />
3.0<br />
0..5--1.0<br />
0.2-1 .o<br />
No reduction<br />
No reduction<br />
No reduction<br />
0.2-0.3<br />
No reduction<br />
800-13, O0OC<br />
Experiment with a 5-curie 137@s Gamma Source<br />
A collimator was constructed by casting lead in<br />
a 4-im-diam steel pipe 48 in. long and providing a<br />
1-in.-diam hole <strong>the</strong> length of thc tube. The collimator<br />
tube was placed in a suitable hole in <strong>the</strong><br />
portable shield which was positioned over a pit<br />
containing a S-curie I3'cs source.<br />
Radiation measurements were made with <strong>the</strong><br />
equipment and source arranged as shown in Fig.<br />
2.3. The radiation source could be raised and<br />
lowered, and <strong>the</strong> collimator tube could be moved<br />
horizontally over <strong>the</strong> source. Weasurcments were<br />
made with <strong>the</strong> source 13 ft and 15 ft 6 in. below<br />
<strong>the</strong> top of <strong>the</strong> portable shield. The source was<br />
about f/4 in. in diameter and 2 in. long and was<br />
enclosed in a 1-in.-diam tube 5 in. deep in <strong>the</strong><br />
carrier.<br />
The results of <strong>the</strong> radiation measurements are<br />
shown in Fig. 2.4. It will be noted that as <strong>the</strong><br />
collimated ion chamber was moved horizontally<br />
over <strong>the</strong> source, <strong>the</strong> radiation readings changed