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Science and Technology of Nuclear Installations
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Science and Technology of Nuclear Installations
/
2021
/
Article
/
Tab 1
/
Research Article
Assessment of Cesium Compound Behavior during Simultaneous Failure of Reactor Pressure Vessels and Spent Fuel Pools Using Modified ART Mod 2: Fukushima Daiichi Accident Simulation
Table 1
Inputs for geometry determination in Modified ART Mod 2.
Volume no.
Diameter (cm)
Height (cm)
Cross-section area (cm
2
)
Volume (cm
3
)
1
4.82
E
+ 02
1.90
E
+ 03
1.81
E
+ 05
3.44
E
+ 08
2
1.40
E
+ 03
3.20
E
+ 03
1.54
E
+ 06
4.92
E
+ 09
3
1.11
E
+ 03
1.18
E
+ 03
9.59
E
+ 05
1.13
E
+ 09
4
4.00
E
+ 03
5.00
E
+ 02
1.16
E
+ 07
6.28
E
+ 07
5
5.50
E
+ 02
2.10
E
+ 03
2.37
E
+ 05
4.99
E
+ 08
6
1.55
E
+ 03
3.40
E
+ 03
1.89
E
+ 06
6.41
E
+ 09
7
1.11
E
+ 03
1.18
E
+ 03
9.59
E
+ 05
1.13
E
+ 09
8
4.64
E
+ 03
5.00
E
+ 02
1.57
E
+ 07
8.31
E
+ 09
9
5.50
E
+ 02
2.10
E
+ 03
2.37
E
+ 05
4.99
E
+ 08
10
1.55
E
+ 03
3.40
E
+ 03
1.89
E
+ 06
6.41
E
+ 09
11
1.11
E
+ 03
1.18
E
+ 03
9.59
E
+ 05
1.13
E
+ 09
12
4.64
E
+ 03
5.00
E
+ 02
1.57
E
+ 07
8.31
E
+ 09
13
4.00
E
+ 06
5.00
E
+ 05
1.26
E
+ 13
6.28
E
+ 18
