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TitleThe 200-Curie Cobalt-60 Gamma -Ray Irradiation Facility forTextile and Polymer Studies (Special Issue on Physical,Chemical and Biological Effects of Gamma Radiation, XI)
Author(s) Ikeda, Tetsuo
Citation Bulletin of the Institute for Chemical Research, KyotoUniversity (1970), 48(1): 45-52
Issue Date 1970-03-31
URL http://hdl.handle.net/2433/76324
Right
Type Departmental Bulletin Paper
Textversion publisher
Kyoto University
Bull. Inst. Chem. Res., Kyoto Univ., Vol. 48, No. 1, 1970
The 200-Curie Cobalt-60 Gamma-Ray Irradiation
Facility for Textile and Polymer Studies
Tetsuo IKEDA
Received Jaanuary 14, 1970
A 200-Curie cobalt-60 gamma-ray irradiation facility for textile and polymer studies was installed at the Institute for Chemical Research, Kyoto University in 1969. This facility is
composed of a source container and gamma-ray irradiation system. As this facility is equi- valent to so-called "gamma cell", can be used even in experimental room without any
special buildings or constructions for prevention of leakages. The leakage of gamma rays of this facility is controlled by lead shieldings below 0.5 mr/h at the surface of the facility.
I. INTRODUCTION
Recently, studies using high energy irradiation are spreading in the field of high polymer chemistry and valuable results are now being obtained in both
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* ith, f i:k;41s : Laboratory of Fiber Chemistry, Institute for Chemical Research, Kyoto Univer- sity, Uji, Kyoto.
( 45 )
T. IKEDA
fundamental and technical studies.The studies of high polymer chemistry using
high energy irradiation may be broadly divided into two classes, namely irradia-
tion polymerization and polymer irradiation.
Chemical improvements of textile properties of various natural and synthetic
fibers by means of graft copolymerization of vinyl monomers, and dynamic
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( 46 )
The 200-Curie Cobalt-60 Gamma-Ray Irradiation Facility
properties or molecular structures such as crystallinity and orientation of some crystalline polymers, for examples polyethylene and polypropylene, are studied in this laboratory using high energy irradiation.
For these purposes, cobalt-60 200-Curie gamma-ray irradiation facility which is relatively simple structure and easy to handle is introduced in this laboratory. Outline of this facility is described briefly in this paper.
II. OUTLINE OF THE FACILITYy
II-1 Cobalt-60 source
Cobalt-60 source manufactured by General Electric Co., U. S. A., is a lmmcb x 1 mm pellet type with specific radioactivity of 20.4 Ci/g. Weight of a pellet is about 7 mg. The cobalt-60 pellets of total 9.8 g . are sealed in a stainless steel capsule shown in Fig. 1.
II-2 Structure This facility may be divided into three parts.
1. Cobalt-60 source container, 2. Source-driving device,
3. Irradiation box. Figure 2 shows the vertical figure of the facility, and Figs. 3 and 4 are the
photographs of the facility. The source container is right side (the position of exposure—normal state) in Fig. 3 and left side (the position of sampling) in Fig. 4, respectively.
II-2. a. Source container
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Fig. 3. Photograph of the facility.Fig. 4. Photograph of the facility. Irradiation state.Sampling state.
( 47 )
T. IKEDA
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( 48 )
The 200-Curie Cobalt-60 Gamma-Ray Irradiation Facility
This container is approximately cylinder type (Fig. 5) and designed to be
used not only as a container for cobalt-60 200-Curie source but also as a trans-
portation container of the source. Inside of the container is made of stainless steel and outside is of normal
iron steel, respectively, and between them lead for leak shielding is packed so
as to control surface leakage below 0.5 mr/h. The source capsule is connected
with a source-driving rod (Fig. 6) . The upper and under sides of the source are
packed with lead rods (about 280 mm length) for prevention of leakage toward upper and under directions. The rod containing the source is stored vertically
in the center portion of the container, and at the time of exposure, the source
capsule together with shielding lead rods are drived down to the bottom of ir-
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( 49 )
T. IKEDA.
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Fig. 8. Photograph of the source-driving device.
radiation chamber by the source-driving device (Fig. 7) .
The container is installed on a truck above the irradiation chamber and
source driving is possible only when the truck (the container) is at right position
above the irradiation box. Putting in and out of samples to be irradiated are
carried out after the truck (the container) is moved manually to left side (com-
pare Fig. 3 with Fig. 4) . II-2. b. Source-driving device
The exposure and housing of the source are made using an gear-driving
mechanism (Figs. 7 and 8), while manual operation can also be conducted through
the handle installed on the control panel. The position of the source is indicated
both by mechanical indicator and pilot lamps installed on the control panel. It requires about 10 sec to exposure the source from the container to the bottom of
the irradiation chamber in the case of electric drive.
II-2. c. Irradiation chamber Size of inner part of the irradiation chamber is about 30 mmm x 320 mm. A
stainless disc with aluminum sample holders is placed at the bottom of the irra-
diation chamber. The sample holders are arranged in five concentric circles ar-
round the source, as shown in Fig. 10. Temperature in the irradiation chamber
is controlled from room temperature to about 100°C by a thermister thermometer
and heaters surrounding the chamber. Lead shieldings surrounding the outer
side of the chamber are used for prevention of leakage at the time of exposure. 1I-2. d. Electric circuit
Figure 9 shows electric circuit for the source driving.
I1-3. Dose rate and leakage
Dose rates at some points were measured with the fluoroglass dosimeter (To-
shiba FD-R1 fluoroglass). Measuring points and results are shown in Fig. 10 and
Table 1, respectively.
Leakages of gamma-rays at the time of exposure were measured using a transistorized GM radiation survey meter (Fujitsu Limited, SM-102). No leakage
over 0.5 mr/h was observed at any points of the surface of the facility.
( 50 )
The 200-Curie Cobalt-60 Gamma-Ray Irradiation Facility
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( 51 )
T. IKEDA
Table 1. Dose rates measured with fluoroglass dosimeter.
Measuring pointsDose rate x 104 (r/h) Li
neNo.Height (mm)
108.26
1607.74 1706 .29 6707.90
(104.15 2{703.95 1l
11704.20 7704.46
(102.52 3}J
l1302.56 1702.63 13702.89 101.55
41401.57 1701 .99 14701.90
(101.10 5{1401.09 1111701.16
14701.34
ACKNOWLEDGENTS
The auther would like to express his sincere gratitude to Professor S. Shimizu
and Mr. R. Katano for their kind supports and suggestions. He is also indebted
to the Kimura Kakoki Co. Ltd. and Mr. T. Utsunomiya for the construction of
this facility.
( 52 )