BACKGROUND OF THE INVENTION
1. Field of the Invention
[0001] This invention relates to a transparent neutron screening material used in gloved
boxes and the like for handling plutonium fuel obtained by reprocessing spent nuclear
fuel from a nuclear power plant.
2. Description of the Prior Art
[0002] Plutonium, like uranium, emits alpha-rays while decaying and at the same time, also
emits gamma-rays and generates neutrons. While further, at the same time, daughter
nuclides generated as a result of decay exist during processing and also emit beta-rays
and gamma-rays. The half life of
239Pu is 2.4×10
4 years, for
240Pu it is 6.6×10
3 years and for
241Pu it is 14 years. This means that the half life of plutonium is shorter than the
half life of
238U, at 4.5×10
9 years and of
235U, at 7×10
8 years. Therefore, the specific radioactivity of such plutonium is about 10
5 times higher than that of uranium. But, on the other hand, plutonium has high toxicity
and, in consideration of its effects on the human body its permissible concentration
of radioactivity is about 1/30 that of uranium.
[0003] Accordingly, in comparison with uranium fuel production facilities, restrictive conditions
resulting from the characteristics of plutonium are imposed on plutonium fuel processing
and its associated facilities. These restrictive conditions are, for example, (1)
the alpha-specific radioactivity is extremely high, as described above; and (2) gamma-ray
intensity and neutron emissions are considerably high.
[0004] This means that sufficient consideration must be given to the handling and management
of plutonium fuel. As for restrictive condition (1), for example, containment management
for containing the plutonium fuel in a gloved box, etc., becomes necessary in order
to avoid inhalation by operators. In other words, the process for shaping plutonium
must be carried out in a completely sealed gloved box under many restrictions, including
restrictions concerning the maintenance and inspection of all machinery and tools
used in the shaping process. Therefore, to produce a MOX (Mixed-Oxide Fuel) pellet
for future use simplification and automation of the production process are more strongly
needed than in the case of uranium processing plants.
[0005] In regard to restrictive condition (2), plutonium obtained from the spent fuel of
a light-water reactor contains large amounts of
240Pu,
241Pu and the like, and the amount of gamma-rays emitted therefrom also increases. Therefore,
to reduce external exposure of the operators, screens of lead, acrylic resins, etc.
must be used.
[0006] Conventional lead glass used in gloved box panels and the like is directed at screening
gamma-rays and is produced according to JIS R-3701 standards. This lead glass has
a chemical composition of, for example, 1 wt% of B, 25 wt% of O, 2 wt% of Na, 16 wt%
of Si, 4 wt% of Ba and 51 wt% of Pb.
[0007] Acrylic plate has also been used as a transparent neutron screening material. Acrylic
plate has a chemical composition consisting of, for example, 8.0 wt% (corresponding
to 0.0952 g/cm
3) of H, 60.0 wt% of O and 32.0 wt% of C.
[0008] Further, lead-containing acrylic resin has been used to screen gamma-rays and neutrons.
Such lead-containing acrylic resin has a chemical composition consisting of, for example,
5.8 wt% of H, 43.8 wt% of C, 20.4 wt% of O and 30.0 wt% of Pb. The properties of such
lead-containing acrylic resin are somewhat inferior, and its reliability is lower
than that of acrylic.
[0009] The intensity of the radiation source described above depends on the isotope composition
of plutonium, and that of isotopes of higher order tends to gradually increase. In
conventional gloved boxes using lead glass or plastic materials, exposure of the operators
is considerably high, and further improvements in screening for the gloved boxes is
currently required. In particular, the existing law stipulates that the dosage rate
should be below 1 mSv/week (below 20 µSv/hour) in areas easily accessed by people
(10 cm from the surface of the gloved box). Therefore, a transparent neutron screening
material having a thickness equal to that of the conventional acrylic resins, lead,
lead-containing acrylic resins and the like, but having higher neutron screening performance,
is required for the application described above.
[0010] It is therefore an object of the present invention to provide a transparent neutron
screening material which can reduce radiation exposure in gloved box operations handling
plutonium fuel, which has high transparency and which can be used for a gloved box,
etc.
[0011] It is another object of the present invention to provide a transparent neutron screening
material which can reduce radiation exposure in gloved box operations handling plutonium
fuel, which has high transparency and high surface wear resistance and which can be
used for a gloved box, etc.
SUMMARY OF THE INVENTION
[0012] A transparent neutron screening material according to a first embodiment of the present
invention comprises a transparent resin plate made of a cyclic olefin copolymer.
[0013] Further, a transparent neutron screening material according to a second embodiment
of the present invention comprises a transparent resin plate made of a cyclic olefin
copolymer, and surface protective layers deposited on both surfaces of the transparent
resin plate having higher wear resistance than the transparent resin plate.
BRIEF DESCRIPTION OF THE DRAWING
[0014] Fig. 1 is a graph showing the relation between the thickness of the transparent neutron
screening plate according to the present invention and a conventional acrylic plate
(thickness: mm) for a
252Cf radiation source plotted against the neutron damping ratio.
DETAILED DESCRIPTION OF THE INVENTION
[0015] The transparent neutron screening material according to the first embodiment of the
present invention provides a transparent resin plate made of a cyclic olefin copolymer.
This transparent resin has a greater hydrogen content, which affects neutron screening
capability, than conventional acrylic resin and the like, and can provide excellent
neutron screening capacity.
[0016] Also, the cyclic olefin copolymer has a bulky alicyclic structure in its main skeletal
structure, is amorphous, has a high glass transition temperature (Tg) and has both
polyolefin resin properties as well as amorphous resin properties.
[0017] Being amorphous, the cyclic olefin copolymer is colorless and transparent, has excel
lent optical characteristics such as birefringence, exhibits the lowest moisture permeation
coefficient among transparent resins, has low water absorbing power but has extremely
high steam resistance, acid/alkali resistance and resistance to polar solvents. Further,
the bending elastic modulus temperature dependence is extremely low, it maintains
high rigidity even at high temperatures, has small molding shrinkage, a low coefficient
of linear expansion, excellent dimensional stability and moldability, and can be molded
by various molding methods such as injection molding, injection blow molding, extrusion
molding, vacuum molding, etc.
[0018] Such a cyclic olefin copolymer is disclosed, for example, in Japanese Patent Publication
No. 4-14685, and is commercially available under the trade name "APEL" ( APL-6509,
APL-6011, APL-6013, and APL-6015) from Mitsui Petrochemical Industries, Ltd.
[0019] As described above, the transparent resin plate made of the cyclic olefin copolymer
used in the first embodiment of the present invention has a high hydrogen content,
has excellent neutron screening capacity and further has excellent moldability. Therefore,
it can be suitably used as a transparent neutron screening material for a gloved box,
etc. However, the resin plate made of the cyclic olefin copolymer used in the first
embodiment of the present invention still has the problem of insufficient wear resistance
on the surface thereof, and is not free from the drawback that the surface of the
resin plate is likely to be damaged if it is used as a transparent neutron screening
material.
[0020] Therefore, the second embodiment of the present invention improves the wear resistance
of the surface of the transparent neutron screening material by employing a three-layered
structure wherein the transparent resin plate made of the cyclic olefin copolymer
is used as a core material, and surface protective layers capable of imparting higher
wear resistance to the surface of the transparent plate are deposited on the surface
thereof.
[0021] This surface protective layer can be deposited by bonding a film to the surface of
the transparent resin plate. Materials for the surface protective layer are not particularly
limited so long as they have higher wear resistance than the transparent resin plate
comprising the core and have radiation resistance. Suitable examples include an acrylic
resin film such as an MMA resin film and hard-coated PET films. The thickness of the
surface protective layer is also not particularly limited, and a suitable thickness
can be selected in accordance with the application of the transparent neutron screening
material. A primer, or the like, can be used for bonding the films.
EXAMPLES
Example 1
[0022] A cyclic olefin copolymer ("APL-6509": a product of Mitsui Petrochemical Industries,
Ltd.) measuring 1,000mm × 1,000mm × 10mm was used as the transparent neutron screening
material for a gloved box panel. This product, APL-6509, had a chemical composition
consisting of 12 wt% of H (corresponding to 0.1224 g/cm
3) and 88 wt% of C.
[0023] The various properties of the resulting transparent neutron screening material were
as follows.
Mechanical properties:
[0024]
| Tensile yield strength (ASTM D638): |
600 kg/cm2 |
| Tensile breaking strength (ASTM D638): |
450 kg/cm2 |
| Tensile elongation at break (ASTM D638): |
30% |
| Bending elastic modulus (ASTM D790): |
25,000 kg/cm2 |
| Bending strength (ASTM D790): |
950 kg/cm2 |
| Izod impact strength: |
|
| with notch (ASTM D256): |
3.5 kgcm/cm |
| without notch (ASTM D265): |
20 kgcm/cm |
| Rockwell hardness (ASTM D785): |
120 (R scale) |
Thermal properties:
[0025]
| Thermal deformation temperature (ASTM D648): |
18.6 kg/cm2 70°C |
| 4.6 kg/cm2 80°C |
| Thermal expansion coefficient (ASTM D649): |
|
| Longitudinal |
7× 10-5 |
| Transversal |
6× 10-5 |
| Molding shrinkage: |
|
| Longitudinal |
0.6% |
| Transversal |
0.5% |
Optical properties:
[0026]
| Light transmission (ASTM D1003: 2 mmt) |
91 |
| Haze (ASTM D1003: 2 mmt) |
2 |
Neutron screening capacity:
[0027] Neutron screening capacity was examined for the transparent neutron screening material
according to the present invention (APL-6509; hydrogen content per unit volume = 0.1224
g/cm
3) and for the conventional acrylic plate (hydrogen content per unit volume = 0.0952
g/cm
3).
Testing conditions:
Radiation source: 252Cf
Thickness of screening material: 10 mm
Measurement time: 30 min.
Results:
[0028]
| |
Damping Ratio |
| Inventive Product |
0.773 |
| Acrylic Plate |
0.841 |
[0029] The results are shown in the graph of Fig.1.
[0030] It can be understood from above that because the transparent neutron screening material
according to the present invention has a hydrogen content of about 30% higher than
that of the conventional transparent neutron screening material made of acrylic resin,
it also has a neutron damping ratio of about 30% higher and a higher neutron screening
capacity.
Example 2
[0031] The transparent neutron screening material of the present invention (Embodiment 2
Product) having a three-layered structure was obtained by bonding 50 µm-thick MMA
resin films to both surfaces of the transparent neutron screening material of Example
1 by using a modified polyolefin resin ("UNISTROL"; a product of Mistui Petrochemical
Industries, Ltd.) as a primer so as to provide surface protective layers.
[0032] A radiation resistance test and a surface wear resistance test were carried out for
the resulting Embodiment 2 Product.
Radiation Resistance Test:
[0033]
| Radiation source: |
| Japan Atomic Energy Research Institute Tokai Research Establishment Reactor JRR-2
Pneumatic Tube highest maximum speed of neutron flux (n/cm2·sec.) |
2.5 × 1012 |
| maximum thermal neutron flux (n/cm2·sec.) |
6.5 × 1013 |
| gamma-rays ratio |
1 × 106 |
Test results:
[0034]
| |
Transparency |
Shape |
Condition of Surface Protective Layer |
| Before irradiation |
Fair |
|
|
| 10 sec. after irradiation |
Fair |
No Change |
No Change |
| 60 sec. after irradiation |
Fair |
No Change |
No Change |
Surface Wear Resistance Test:
[0035] The surface wear resistance test was carried out in the following way.
(a) The haze of the screening material sample obtained in the manner described above
was measured in accordance with ASTM D1003.
(b) A 100 mm × 100 mm screening material sample was cut and a hole having a diameter
of 6 mm was opened at the center.
(c) The screening material sample was conditioned for 48 hours at a temperature of
23°C and a humidity of 50%.
(d) The screening material sample was kept in contact with an abrasive wheel (CS10F,
load: 250g × 2 = 500g), while the abrasive wheel was rotated 500 times by an abrasion
tester ["Rotary Abrasion Tester", a product of Toyoseiki Seisakusho Co., Ltd.]. The
surface condition of the abrasive wheel was adjusted in advance by contacting the
wheel with sand paper.
(e) After the screening material sample was washed with water and dried, haze was
measured in the same way as described above in step (a).

Further, the lower the ΔH% value, the higher the surface wear resistance of the surface.
Test results:
[0036]
| |
Embodiment 2 Product |
Transparent Resin Plate (core material) |
| ΔH% |
15 |
70 |
Example 3
[0037] A transparent neutron screening material of the present invention having surface
protective layers (Embodiment 3 Product) was produced by bonding a hard-coated PET
film having a thickness of 100 µm to both surfaces of a transparent resin plate (thickness:
10 mm) made of a cyclic olefin copolymer (APL-6509) using "UNISTOLE" (a product of
Mitsui Petrochemical Industries, Ltd.) as the primer.
[0038] A radiation resistance test and a surface wear test were carried out for the resulting
Embodiment 3 Product in the same manner as in Example 2.
Radiation resistance test results:
[0039]
| |
Transparency |
Shape |
Condition of Surface Protective Layer |
| Before irradiation |
Fair |
|
|
| 10 sec. after irradiation |
Fair |
No Change |
No Change |
| 60 sec. after irradiation |
Fair |
No Change |
No Change |
Surface wear resistance test results:
[0040]
| |
Embodiment 3 Product |
Transparent Resin Plate (core material) |
| ΔH% |
13 |
70 |
[0041] The transparent neutron screening material according to the first embodiment of the
present invention has high neutron screening capacity and is suitable as, for example,
a transparent neutron screening material for gloved box panels.
[0042] The transparent neutron screening material according to the second embodiment of
the present invention has high neutron screening capacity and excel lent surface wear
resistance and is suitable as, for example, a transparent neutron screening material
for gloved box panels.