ML21038A001

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Alpha-Omega Services, Inc, Chapter 2, Structural Evaluation
ML21038A001
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Issue date: 01/31/2021
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Radioactive Material Transport Packaging System Safety Analysis Report 2-1 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2 STRUCTURAL EVALUATION This chapter presents the structural evaluation of the AOS Transport Packaging System, and demonstrates that the design meets all applicable structure criteria. All components that comprise the AOS Transport Packaging System are evaluated to their regulatory requirements. Normal conditions of transport (NCT) and Hypothetical Accident conditions (HAC) of transport are applied, in accordance with 10 CFR 71 and IAEA TS-R-1 requirements (References [2.1] and [2.2], respectively). Analyses comply with the methodology presented in Regulatory Guide 7.6, and loadings are combined, as provided in Regulatory Guide 7.8 (References [2.3] and [2.4], respectively).

Engineering Analyses - Most of the engineering analyses are conducted using Finite Element Methods (FEM). The computer program applied in the analysis, LIBRA, is a multi-purpose finite element program applicable to static and dynamic analyses of linear and non-linear structural systems. A detailed description of the LIBRA program and a summary of the verification and qualification studies conducted in support of this evaluation are provided in Appendix 2.12.3.

The Finite Element Analyses (FEA) are primarily concentrated on the cask structure, due to its containment functions. For the evaluated conditions, finite element analyses and appropriate material properties are used. For all drop conditions, the deceleration forces are determined using finite element methods. Load distributions are obtained for the Drop Test results. Results from the analyses demonstrate that all AOS Transport Packaging System models have the capability to meet regulatory requirements.

Free-Drop Test - Free-Drop tests are conducted to verify the analytical procedure(s) used to determine cask impact accelerations, and forces within the impact limiter and cask structures for three (3) drop orientations. The drop tests also confirm the distribution of impact forces upon the cask structure.

Component Tests - Component tests are conducted to enhance and/or verify understanding of materials and the behavior of AOS Transport Packaging System components under design conditions.

A summary of the engineering evaluation analyses conducted upon each AOS Transport Packaging System model is provided in Table 1-4, AOS Transport Packaging System Analyses Summary -

All Models.

2-2 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

2.1 DESCRIPTION

OF STRUCTURAL DESIGN 2.1.1 Discussion The AOS Transport Packaging System encompasses a group of transport packaging, scaled from the Model AOS-100 transport package. There are variations between models in the use of shielding materials (tungsten alloy or carbon steel), the size and number of bolts, and the density of the polyurethane foam used as a thermal shielding and energy absorbing material. The cask structure is the only true scale of the basic design, with minor variations to accommodate standard size components and/or features.

The AOS Transport Packaging System consists of three (3) main components that are important to safely operate the transport packages - cask, impact limiter, and cask lid elastomeric or metallic seal:

Cask - The cask body, together with the cask drain port closure, cask vent port closure, and cask lid seal joint, provide containment for the radioactive contents that are stored and transported within the transport package. (Refer to Figure 4-1, Containment Boundary (Cask Lid Metallic Seal Shown), for a depiction of the containment boundary.) The cask body is constructed of 300 series stainless steel (SS300) material.

Tungsten alloy or carbon steel material is embedded within the cask body and cask lid plug, to enhance the assembled casks shielding capability. This option of shielding materials are variable within the AOS Transport Packaging System models, dependent upon the isotope being transported. Refer to Figure 2-1 through Figure 2-3 for cutaway views of the Model AOS-025, AOS-050, and AOS-100, packaging, respectively, and to Figure 2-4 for an isometric view of a typical AOS cask.

Impact Limiter - The impact limiter consists of two (2) sections, attached to one another by mechanical connectors. Each impact limiter section covers one end of the cask. The impact limiters are constructed of SS300 thin shell, filled with polyurethane foam, and mitigate mechanical and thermal loads generated during Normal and Hypothetical Accident conditions of transport. Refer to Figure 2-5 for an isometric view of a typical AOS impact limiter.

Cask Lid Seal - All transport package models use either a pair of elastomeric O-Rings captured within one (1) or two (2) SS300 series flat rings, or metallic double C cross-section arrangement. The cask lid metallic seal is a multiple-component assembly consisting of a nickel-chromium alloy spring and silver liner. Additional information specific to the cask lid seal is provided in Subsection 4.1.3, Cask Lid Seal.

Refer to Section 1.2, Package Description, for further details regarding the packaging.

The evaluation presented here is for three (3) model sizes - AOS-025A, AOS-050A, and AOS-100A and AOS-100B. The Model AOS-100A analyses are also applicable to the Model AOS-100A-S, a double-ended configuration with a cask lid and cask lid plug at both ends, because each variation of this model effectively has the same weight.

Radioactive Material Transport Packaging System Safety Analysis Report 2-3 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-1. Assembled Transport Package Cutaway - Model AOS-025A IMPACT LIMITER IMPACT LIMITER PALLET LINER SHIELDING MATERIAL (TUNGSTEN ALLOY)

SHIPPING CAGE CASK LID ATTACHMENT

BOLTS, CASK LID, CASK LID SEAL, CASK LID PLUG TIE-DOWN STRAPS CASK

2-4 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-2. Assembled Transport Package Cutaway - Model AOS-050A IMPACT LIMITER PALLET SHIELDING MATERIAL (TUNGSTEN ALLOY)

CASK LID ATTACHMENT

BOLTS, CASK LID, CASK LID SEAL, CASK LID PLUG TIE-DOWN TURNBUCKLE IMPACT LIMITER CASK SHIPPING CRADLE SHIPPING CAGE TIE-DOWN TURNBUCKLE

Radioactive Material Transport Packaging System Safety Analysis Report 2-5 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-3. Assembled Transport Package Cutaway - Models AOS-100A and AOS-100B Note: Model AOS-100A-S is not shown, because of its similarity to the Model AOS-100A.

IMPACT LIMITER PALLET SHIELDING MATERIAL (TUNGSTEN ALLOY OR CARBON STEEL)

SHIPPING CAGE CASK LID ATTACHMENT

BOLTS, CASK LID, CASK LID SEAL, CASK LID PLUG TRUNNION IMPACT LIMITER CASK TIE-DOWN TURNBUCKLE SHIPPING CRADLE PIN SUPPORT &

LATCH PIN

2-6 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-4. Isometric View - Typical Cask CASK LID SEAL

Radioactive Material Transport Packaging System Safety Analysis Report 2-7 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-5. Isometric View - Typical Impact Limiter SPHERICAL DISH CYLINDRICAL RING COVER PLATE POLYURETHANE FOAM OUTER CYLINDRICAL RING SWIVEL HOIST RING WIRE ROPE SWAGE SOCKET ASSEMBLY BACK PLATE INNER PLATE CYLINDRICAL RING CONICAL RING RIBS TURNBUCKLE SPACERS

2-8 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.1.2 Design Criteria This subsection defines the allowable stress in accordance with Regulatory Guide 7.6 (Reference [2.3]),

for Load Combinations defined in Regulatory Guide 7.8 (Reference [2.4]). Table 2-1 presents a summary of the Load Combinations for Normal and Hypothetical Accident conditions of transport, and lists the FEA models used in the evaluation. The Load Combinations presented in Table 2-1 are adapted from Reference [2.4], with some additions to reflect current regulatory requirements. The Normal and Hypothetical Accident conditions of transport design criteria for stress are obtained from Reference [2.3].

Under Normal conditions of transport, the following design criteria apply:

Pm < Sm Pm + Pb < 1.5 Sm Pm + Pb + Q < 3.0 Sm Under Hypothetical Accident conditions of transport, the following design criteria apply:

Pm lesser of 2.4 Sm, or 0.7 Su Pm + Pb lesser of 3.6 Sm, or Su where:

Sm

=

Allowable Primary Membrane Stress Pm

=

Primary Membrane Stress Pb

=

Primary Bending Stress Q

=

Secondary Thermal Stress Su

=

Ultimate Stress The above criteria is consistent with Reference [2.3]. The Margin of Safety is provided by:

MS

=

(F / f) - 1.0 where:

F

=

Allowable Stress f

=

Calculated Stress

Radioactive Material Transport Packaging System Safety Analysis Report 2-9 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-1 lists the Load Combinations and other factors (Normal and Hypothetical Accident conditions of transport) that serve as design criteria. Each Normal and Hypothetical Accident condition of transport is analyzed, using various Load Combinations to demonstrate performance. Specific Load Combinations are grouped using unique designators (for example, Load Combination 101 refers to the specific combination of Ambient Temperature of 38°C, Maximum Decay Heat, Zero Insolation, and Minimum Internal Pressure).

Table 2-6 summarizes the Load Combinations used in the analyses.

Allowable material properties are obtained from the ASME Code (Reference [2.5]) for ferrous materials, and from the manufacturers data for tungsten alloy and polyurethane foam materials. The impact load evaluation is based upon limiting the forces transferred to the cask components during the event, to a level well below the casks capacity to safely carry the load. Each AOS Transport Packaging System model is designed for specific pressures, based upon the cavity geometry and proposed payload.

In addition to the design criteria presented above, the following failure modes are also considered:

Brittle Fracture Fatigue Buckling These topics are described in Paragraph 2.1.2.1 through Paragraph 2.1.2.3.

Impact evaluations are provided by FEA models, as described in Paragraph 2.1.2.4.

Refer to Table 2-8 for a breakdown of the AOS Transport Packaging System, by component. The table lists the applicable Code or Standard, as well as the applicable Safety Classification.

2-10 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-1. Summary of Load Combinations for Normal and Hypothetical Accident Conditions of Transport Evaluation Conditions Load Combinationsa Ambient Temperature Decay Heat Insolation Internal Pressure Fabrication Stresses 38°C (100°F)

- 29°C

(-20°F)

-40°C

(-40°F)

Max.

Zero Max.

Zero Max.

Min.

Normal Conditions of Transport (Analyzed Individually)

Hot Environment 101 101 101 101 211 102 102 102 201 102 211 Cold Environment 103 103 103 103 211 104 104 104 104 211 105 105 105 211 106 106 106 211 Internal Design Pressure (varies by model) 102 102 102 201 211 Reduced External Pressure -

24.5 kPa (3.5 psia) 102 102 102 202 211 Increased External Pressure -

140 kPa (20 psia) 103 103 103 203 103 211 Compression Load (5x weight) 215 101 101 201 201 211 Rod Drop onto Cask 216 101 101 201 211 216 104 104 201 211 Vibration, Forward Load 221 102 102 201 211 221 103 103 103 103 211 Vibration, Lateral Load 222 102 102 201 211 222 103 103 103 103 211 Vibration, Vertical Load 223 102 102 201 211 223 103 103 103 103 211 3-or 4-ft.

Head-On Drop 231 102 102 102 201 201 211 Impact Test 232 102 102 201 211

Radioactive Material Transport Packaging System Safety Analysis Report 2-11 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Hypothetical Accident Conditions of Transport (Apply Sequentially)

Free Drop Head-On Orientation 301 102 102 201 211 Side Orientation +

Slap-Down 302 102 102 201 211 305 104 104 104 211 Cg/Corner Orientation 303 102 102 201 211 306 104 104 104 211 Puncture 311 101 101 201 211 Thermal 211 Fire at 30 minutes 111 102 102 201 211 Post Fire at 60, 90, 120, 150, and 180 minutes 112 102 102 201 211 Deep Water Immersion 204 101 101 201 211

a. Numbers refer to a specific Load Condition (Case). For example, Load Case 101 refers to a condition in which the environment conditions are 38°C (100°F) ambient temperature, zero (0) insolation, maximum decay heat, and zero (0) internal pressure.

Table 2-1. Summary of Load Combinations for Normal and Hypothetical Accident Conditions of Transport (Continued)

Evaluation Conditions Load Combinationsa Ambient Temperature Decay Heat Insolation Internal Pressure Fabrication Stresses 38°C (100°F)

- 29°C

(-20°F)

-40°C

(-40°F)

Max.

Zero Max.

Zero Max.

Min.

2-12 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.1.2.1 Brittle Fracture Brittle fracture is not considered in this evaluation, because all containment and non-containment structural components are fabricated of SS300. SS300 does not undergo ductile-to-brittle transition in the temperature range of interest [down to -40°C (-40°F)]; therefore, it is safe from brittle fracture.

The cask lid attachment bolts are fabricated from ASME SB-637, UNS N07718. This material is also excluded from brittle fracture consideration, in accordance with Section III, Division 1, paragraph NB-2311(a)(7) in Reference [2.26].

2.1.2.2 Fatigue The fatigue evaluation is limited to bolts that experience both preload shock and vibration loading during transportation. Pressurization and thermal loads do not significantly contribute to fatigue loading, because of their magnitude and long vibration period.

The allowable fatigue stress, Salt, of package components corresponds to the number of vibration cycles. The design fatigue curve is provided in Reference [2.14], Section 5, Figure 1-9.2. The value of Salt is corrected by the ratio of the modulus of elasticity provided on the design fatigue curve to the modules of elasticity of the component material used in the analyses.

Radioactive Material Transport Packaging System Safety Analysis Report 2-13 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.1.2.3 Buckling The AOS Transport Packaging System cask shells are not likely to experience buckling instability, based upon their R/t ratio due to forces generated under Normal and Hypothetical Accident conditions of transport. However, because buckling is an unacceptable failure mode for the containment boundary (located within the cask component of the transport package), per Reference [2.3], the buckling critical force, Fcr, is calculated for each packaging system model, in Table 2-2.

Cask buckling under external loading requires the cask outer shell to buckle. Buckling of the cask outer shell, under compressive loading, is conservatively evaluated using the formula provided in Reference [2.6].

The reference formula for cylinder buckling under axial load is:

Fcr = k

  • E
  • t / r (2-1) with the coefficient k = 0.182.

The well-known solution for buckling of a cylinder under axial load [2.6] is:

CR = [2kcE / 12 (1 - 2)] (t / L)2 (2-2) where, for moderate-length cylinders:

kc = 0.702

  • Z (2-3)

Z = (1-2)

  • L2 / R
  • t (2-4)

The Z parameter in Equation 2-4 defines the cylinder length category - short, moderate, or long. The Z parameter is the same for all three (3) model sizes - AOS-025, AOS-050, and AOS-100 - because of their scale relationship:

Z = 14.5 This places the AOS cylinders in the short-to-moderate length category. For E = 28.0 x 106, Equations 2-2, 2-3, and 2-4 provide:

kc = 11.0 CR = 6.98 x 106 psi

2-14 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

For short-to-moderate length cylinders with Z = 14.5, column buckling mode is precluded. Buckling stress under compressive load is then provided by:

CR = 0.6 E t / R (2-5)

CR = 6.87 x 106 psi The above two solutions for CR demonstrate that Equation 2-1 is an alternative to Equation 2-2 for buckling stress in short-to-moderate-length cylinders. The coefficient 0.6 in Equation 2-5 is applicable to perfect cylinders - cylinders with no variation in radius and thickness. For imperfect cylinders, a smaller coefficient must be used. The value in Equation 2-1, 0.182, is applicable to thin cylinders, and is conservative for thick cylinders such as the three (3) AOS casks.

The high Fcr values listed in Table 2-2 preclude buckling failure.

Table 2-2. Buckling Stress Values - All Modelsa

a. The equation used for buckling stress is Fcr = 0.182 E
  • t / r.

Model Young Module of Elasticity, E at 25.6°C (78°F)

(psi)b

b. Considering E at -100°F, 29.2 x 106, the value of Fcr increases by 4%.

Considering E at 600°F, 25.3 x 106, the value of Fcr decreases by 10%.

Wall Thickness, t

(in.)

Cylinder Radius, r

(in.)c c.

r is the average radius through wall thickness, [(Outside Diameter - Inside Diameter) / 2].

Buckling Critical Force, Fcr (psi)b AOS-025 28 x 106 1.5 2.75 2.78 x 106 AOS-050 28 x 106 3.0 5.5 2.78 x 106 AOS-100 28 x 106 6.0 11.0 2.78 x 106

Radioactive Material Transport Packaging System Safety Analysis Report 2-15 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.1.2.4 FEA Models Three (3) Finite Element Analysis (FEA) analytical models are used in the stress analyses of the Model AOS-025, AOS-050, and AOS-100 transport packages - axisymmetric (2D) and 3D models of the cask component and a 3D model of the impact limiter component - for each AOS Transport Packaging System model. The cask component FEA models are used to evaluated the symmetric and non-symmetric loading condition on the cask, while the impact limiter FEA model is used to establish the free drop condition-limiting force.

The 2D model of the cask contains approximately 5,500 nodes and 5,500 elements, and is represented in Figure 2-6. The 3D model of the cask contains approximately 72,700 nodes and 66,400 elements, and is represented in Figure 2-7. A rendered plot of the 3D model of the cask is illustrated in Figure 2-8. The 3D model of the impact limiter is presented later, in Figure 2-32.

The 3D model is generated by rotation of the 2D model about the cask longitudinal axis. In this way, the 2D and 3D models are compatible for stress combinations that involve both 2D and 3D models. The 3D model is composed of 12 identical sections, over a 180° azimuth. In all 3D analyses, there is symmetry around the 0 to 180° meridian plane, requiring only a 180° model. The nodal and element numbers are defined such that adjacent meridian node and element numbers differ by 10,000. Quad and triangular elements in the 2D model are transformed into solid brick and wedge elements in the 3D model. Spring elements are preserved in the 3D model, and gaps are assumed closed in 3D analyses.

Figure 2-6. Axisymmetric (2D) Model - Models AOS-025, AOS-050, and AOS-100

2-16 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-7. 3D Model - Models AOS-025, AOS-050, and AOS-100 Figure 2-8. 3D Rendered Model - Models AOS-025, AOS-050, and AOS-100

Radioactive Material Transport Packaging System Safety Analysis Report 2-17 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.1.2.4.1 Stress Monitoring Locations The Model AOS-025, AOS-050, and AOS-100 transport packages have 22 stress monitoring locations, illustrated in Figure 2-9. Each location is a cross-section of an inside or outer shell, containing several elements. Table 2-3 lists the elements that comprise each cross-section.

Force and moment resultants at each monitored cross-section are evaluated by integrating the element stresses in the cross-section elements. In the LIBRA FEA program, element stresses are output at element Gaussian integration points, and the integrations for force and moment resultants are based upon the stress and geometry data at the gauss points. The integrated force and moment resultants are used to determine Pm and Pb stresses for the monitored cross-section.

In 3D analyses, stress is evaluated at monitoring locations in each of the 12 azimuth sections. Therefore, stresses are evaluated at 12 times (12x) the number of locations used in 2D analyses. The maximum values found in any of the 12 azimuth sections are used in forming stress combinations.

Figure 2-9. Pm and Pb Stress Monitoring Points - All Models 1

2 3

7 8

9 10 11 12 13 14 21 4

5 6

20 19 18 15 16 17 22

2-18 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-3. Pm and Pb Stress Monitoring Section Elements - All Models Section Elements 1

1957, 1958, 1959, 1960, 1961, 1962, 1963, 1964, 1965, 2146, 2147, 2148, 2149, 2150, 2151, 2152, 2153, 2154, 2155 2

552, 904, 905, 906, 907, 908, 909, 910, 911, 912, 1587, 1588, 1589, 1590, 1591, 1592, 1593, 1594, 1595, 1596 3

348, 349, 350, 351, 352, 353, 354, 355, 356, 507, 508, 509, 510, 511, 512, 513, 514, 515, 516 4

4587, 4591, 4595, 4599 5

4572, 4575, 4578, 4581 6

4552, 4553, 4554, 4555 7

4476, 4477, 4478, 4479 8

4408, 4409, 4410, 4411 9

4344, 4345, 4346, 4347 10 4280, 4281, 4282, 4283 11 4141, 4150, 4159, 4168, 4177, 4186, 4195 12 4133, 4142, 4151, 4160, 4169, 4178, 4187 13 4212, 4215, 4218, 4221 14 4214, 4217, 4220, 4223 15 5218, 5236, 5254 16 5235, 5253, 5271 17 5214, 5215, 5216, 5217 18 5166, 5167, 5168, 5169 19 5140, 5143, 5146, 5149 20 5122, 5126, 5130, 5134 21 3001, 3017, 3033, 3049, 3065, 3081, 3097 22 3190, 3208, 3226, 3244

Radioactive Material Transport Packaging System Safety Analysis Report 2-19 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.1.2.4.2 Load Cases and Load Combinations Table 2-4 lists the 31 Load Cases (18 Normal, and 13 Hypothetical Accident, conditions of transport) involved in evaluating each AOS Transport Packaging System model. Each Load Case represents specific conditions of transport. Table 2-5 summarizes the numbering designations for these Load Cases. These Load Cases are then combined as Load Combinations in Table 2-6.

The 2D model is the predominate model used in the stress analyses of the 31 Load Cases. The 3D model is used to evaluate stress for analysis of vibration and shock loadings, as well as for Side and Cg/Corner Drop loadings.

The 31 Load Cases are combined into 34 Load Combinations (19 Normal, and 15 Hypothetical Accident, conditions of transport), listed in Table 2-6. Load Combinations numbered 100 to 299 are used for Normal conditions of transport. Load Combinations numbered 300 to 399 are used for Hypothetical Accident conditions of transport.

Table 2-4. Load Cases Conditions of Transport Load Case Description Normal 101 100°F Ambient, Maximum Decay Heat 102 100°F Ambient, Maximum Decay Heat, Maximum Insolation 103

-20°F Ambient, Zero Decay Heat, Zero Insolation 104

-40°F Ambient, Zero Decay Heat, Zero Insolation 105

-40°F Ambient, Maximum Decay Heat 106

-20°F Ambient, Maximum Decay Heat 201 Internal Design Pressure Model AOS-025 -

Model AOS-050 -

Model AOS-100 -

207 kPa (30 psia) 414 kPa (60 psia) 1,930 kPa (280 psia) 202 Minimum External Pressure, 24 kPa (3.5 psia) 203 Maximum Increased External Pressure, 140 kPa (20 psia) 204 Additional Increased External Pressure, 2 MPa (290 psia) 211 Fabrication Stress 215 Compression Load (5x weight) 216 Rod Drop onto Cask 221 Forward 10g Vibration Inertia Load 222 Lateral 5g Vibration Inertia Load 223 Vertical 2g Vibration Inertia Load 231 Head-On Drop Model AOS-025 -

Model AOS-050 -

Model AOS-100 -

4-ft. Head-On Drop 4-ft. Head-On Drop 3-ft. Head-On Drop 232a 30-ft. Head-On Drop Impact Test, Normal Conditions

2-20 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Hypothetical Accident 111 Fire at 30 Minutes, 1,475°F Ambient, Maximum Decay Heat 112 Post Fire at 60 Minutes, 100°F, Maximum Decay Heat, Maximum Insolation Post Fire at 90 Minutes, 100°F, Maximum Decay Heat, Maximum Insolation Post Fire at 120 Minutes, 100°F, Maximum Decay Heat, Maximum Insolation Post Fire at 150 Minutes, 100°F, Maximum Decay Heat, Maximum Insolation Post Fire at 180 Minutes, 100°F, Maximum Decay Heat, Maximum Insolation 301 30-ft. Head-On Drop 302 30-ft. Side Drop + Slap-Down 303 30-ft. Cg/Corner Drop 304 30-ft. Head-On Drop at -40°F, Low Temperature 305 30-ft. Side Drop + Slap-Down at -40°F, Low Temperature 306 30-ft. Cg/Corner Drop at -40°F, Low Temperature 311 4-ft. Drop onto Rod

a. Load Combination 232 is documented only for the Model AOS-025A and AOS-050A transport packages, and demonstrates compliance with the requirements of IAEA TS-R-1, Paragraph 737 (Reference [2.2]).

Table 2-5. Load Case Designation Summary Conditions of Transport Designating Number Load Case Designation Normal 101 to 106 Thermal Loading 201 to 204 Pressure Loading 211 Fabrication Stress Loading 215 Compression Load 216 Rod Impact Loading 221 to 223 Vibration and Shock Loading 231 3-or 4-ft. Drop Loading 232a

a. Load Combination 232 is documented only for the Model AOS-025 and AOS-050 transport packages, and demonstrates compliance with the requirements of IAEA TS-R-1, Paragraph 737 (Reference [2.2]).

Impact Test, Normal Condition Hypothetical Accident 111 and 112 Fire Accident 301 to 306 30-ft. Accident Drop Loading 311 4-ft. Accident Drop Loading Table 2-4. Load Cases (Continued)

Conditions of Transport Load Case Description

Radioactive Material Transport Packaging System Safety Analysis Report 2-21 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-6. Load Combinations Conditions of Transport Load Combination Load Casesa Description Normal 101 102, 201, 211 Hot Environment 102 104, 201, 211 Cold Environment 103 103, 202, 211 Increased External Pressure 104 101, 201, 202, 211 Minimum External Pressure 105 105, 201, 202, 211 Cold Environment with Maximum Decay Heat 106 101, 201, 203, 211 Maximum Pressure, Hot Environment 107 105, 201, 203, 211 Maximum Pressure, Cold Environment 215 215, 101, 201, 211 Compression Load 216 216, 101, 201, 211 Rod Drop 217 216, 104, 201, 211 Rod Drop, Cold Environment 221 221, 101, 201, 211 Forward Vibration 222 222, 101, 201, 211 Lateral Vibration 223 223, 101, 201, 211 Vertical Vibration 224 221, 103, 201, 211 Forward Vibration at Cold Temperature 225 222, 103, 201, 211 Lateral Vibration at Cold Temperature 226 223, 103, 201, 211 Vertical Vibration at Cold Temperature 231 231, 102, 201, 211 Head-On Drop, Normal Conditions Model AOS-025 -

Model AOS-050 -

Model AOS-100 -

4-ft. Head-On Drop, Normal Conditions 4-ft. Head-On Drop, Normal Conditions 3-ft. Head-On Drop, Normal Conditions 232b 232, 102, 201, 211 30-ft. Head-On Drop, Normal Conditions (Impact Test) 233 231, 103, 211 Drop at Cold Temperature Model AOS-025 -

Model AOS-050 -

Model AOS-100 -

4-ft. Drop at Cold Temperature 4-ft. Drop at Cold Temperature 3-ft. Drop at Cold Temperature

2-22 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Hypothetical Accident 301 301, 102, 201, 211 Head-On Drop Orientation 302 302, 102, 201, 211 Side Drop Orientation 303 303, 102, 201, 211 Cg/Corner Drop Orientation 304 304, 105, 202, 211 Head-On Drop Orientation at -40°F, Cold Environment 305 305, 105, 202, 211 Side Drop Orientation at -40°F, Cold Environment 306 306, 105, 202, 211 Cg/Corner Drop Orientation at -40°F, Cold Environment 310 204, 101, 211 Additional Increased External Pressure (290 psi) 311 311, 101, 201, 211 4-ft. Drop onto Rod 312 311, 104, 201, 211 4-ft. Drop onto Rod at -40°F, Cold Environment 350 111, 201, 211 Fire at 30 Minutes 351 112, 201, 211 Post Fire at 60 Minutes 352 Post Fire at 90 Minutes 353 Post Fire at 120 Minutes 354 Post Fire at 150 Minutes 355 Post Fire at 180 Minutes

a. Some Normal conditions of transport Load Cases are included in Hypothetical Accident conditions of transport Load Combinations, to meet regulatory requirements.
b. Load Combination 232 is documented only for the Model AOS-025 and AOS-050 transport packages, and demonstrates compliance with the requirements of IAEA TS-R-1, Paragraph 737.66 (Reference [2.2]).

Table 2-6. Load Combinations (Continued)

Conditions of Transport Load Combination Load Casesa Description

Radioactive Material Transport Packaging System Safety Analysis Report 2-23 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.1.3 Weights and Centers of Gravity Table 2-7 lists the package weight and center of gravity of each AOS Transport Packaging System model.

The package is defined as the assembly of two (2) impact limiters and their mechanical connectors, the cask, and the cask contents. The content weight includes the weight of the radioactive materials, plus the weight of any shielding devices and shoring devices, if used in the assembly. The content weight excludes the weight of the shipping cage, pallet or shipping cradle, and tie-down hardware.

Figure 2-10, Figure 2-11, and Figure 2-12 illustrate the AOS Transport Packaging System center of gravity for the Model AOS-025, AOS-050, and AOS-100 transport packages, respectively.

Table 2-7. AOS Transport Packaging System Maximum Authorized Package Weight and Cg Locations - All Models Model Category Maximum Authorized Package Weight (kg / lbs.)

Cg Locationsa (cm / in.)

a. AOS Transport Packaging System center of gravity. Refer to Figure 2-10, Figure 2-11, and Figure 2-12 for the Model AOS-025, AOS-050, and AOS-100 transport packages, respectively.

Packageb

b. Authorized package weight includes the components listed in this table; however, not all components will be at maximum weight.

Impact Limitersc c.

Includes the weight of both impact limiters.

Caskd

d. Includes the weight of the contents.

Contents

Pallet, Shipping Cage, and Tie-Down Devices X

Y Z

AOS-025A I

100 13 64 4.5 24.9 19.05 26.97 22.86 220 28 140 10 55 7.50 10.62 9.00 AOS-050A I

681 56 480 27 135.2 45.41 46.22 41.57 1,500 123 1,058 60 298 17.88 18.20 16.37 AOS-100A I

5,675 467 3,850 227 1,685.1 77.39 87.68 77.39 12,500 1,029 8,481 xxx500 3,715 30.47 34.52 30.47 AOS-100B II 4,994 467 3,192 227 1,685.1 77.39 87.68 77.39 11,000 1,029 7,030 500 3,715 30.47 34.52 30.47 AOS-100A-S I

5,675 467 3,850 227 1,685.1 77.39 87.68 77.39 12,500 1,029 8,481 500 3,715 30.47 34.52 30.47

2-24 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-10. Center of Gravity - Model AOS-025 Note: Dimensions are in inches.

10.6 7.5 9.0 (21.4)

(TOP VIEW)

(SIDE VIEW)

(18.0)

(18.0)

Radioactive Material Transport Packaging System Safety Analysis Report 2-25 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-11. Center of Gravity - Model AOS-050 Note: Dimensions are in inches.

(TOP VIEW)

(SIDE VIEW)

(35.8)

(35.8)

(17.9)

(36.6)

(18.2)

(16.4)

2-26 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-12. Center of Gravity - Model AOS-100 Note: Dimensions are in inches.

(61)

(61)

(71.7)

(TOP VIEW)

(SIDE VIEW)

(30.5)

(34.5)

(30.5)

Radioactive Material Transport Packaging System Safety Analysis Report 2-27 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.1.4 Identification of Codes and Standards for Package Design Table 2-8 presents the applicable Codes and Standards for design, fabrication, and testing of the AOS Transport Packaging System, broken down by component category or functionality. For each category, the table addresses the applicable Code and/or Standard, as well as the Safety Classification.

Table 2-8. Applicable Codes and Standards for Design, Fabrication, and Testing of the AOS Transport Packaging Systema Package Components or Features Component Safety Group Containment Criticalityb Other Safety Cask Cavity Shell, Port Plugs, Threaded Pipe Plugs, Cask Lid Attachment Bolts Cask Lid Seal Criticality Liner Cask Shielding (Tungsten Alloy or Carbon Steel)

Cask Outer Shell, Cask Lid Plug, Bottom Plate, Plate Shell Port Plug Sealsc Neutron Shielding, Liner Cask Trunnion Tie-Down Devices Impact Limiters Safety Classification A

A A

B B

B B

B B

A B&PV Code Section Section III, Division 1, Subsection NB Section III, Division 1, Subsection NG Section III, Division 1, Subsection NF Section

VIII, Division 1 Material Requirements NB-2000 NG-2000 AMS-T-
21014, Class 3 NF-2000 NF-2000 NF-2000 NF-2000 UG Forming, Fitting, and Aligning NB-4200 NG-4200 NF-4200 NF-4200 NF-4200 NF-4200 UG Welding NB-4400 NG-4400 NF-4400 NF-4400 NF-4400 NF-4400 UW Qualification of Weld Procedure and Personnel NB-4300 NG-4300 NF-4300 NF-4300 NF-4300 NF-4300 UW Weld Heat Treatment NB-4600 NG-4600 NF-4600 NF-4600 NF-4600 NF-4600 UW

2-28 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Examination NB-5000 NG-5000 NF-5000 NF-5000 NF-5000 NF-5000 UW/UG Acceptance Testing NB-6000 ANSI N14.5 Straight Beam method per NG-2532.1,Section III, Division 1, 2001 Edition with 2003 Addendum Per Applicable Code Standards ANSI N14.5 ANSI N14.6 ANSI N14.6 Per Table 8-1

a. This table is derived from NUREG/CR-3854, Fabrication Criteria for Shipping Containers (Reference [2.24]).
b. Criticality does not apply to the AOS Transport Packaging System.

c.

Port plug seals includes the conical seals.

Table 2-8. Applicable Codes and Standards for Design, Fabrication, and Testing of the AOS Transport Packaging Systema (Continued)

Package Components or Features Component Safety Group Containment Criticalityb Other Safety Cask Cavity Shell, Port Plugs, Threaded Pipe Plugs, Cask Lid Attachment Bolts Cask Lid Seal Criticality Liner Cask Shielding (Tungsten Alloy or Carbon Steel)

Cask Outer Shell, Cask Lid Plug, Bottom Plate, Plate Shell Port Plug Sealsc Neutron Shielding, Liner Cask Trunnion Tie-Down Devices Impact Limiters

Radioactive Material Transport Packaging System Safety Analysis Report 2-29 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.2 MATERIALS 2.2.1 Material Properties and Specifications As previously discussed in Subsection 2.1.1, the allowable material properties used in the structural evaluation are obtained from Reference [2.5] for ferrous materials, and from the manufacturers data for tungsten alloy and polyurethane foam materials.

The AOS Transport Packaging System is designed using the following materials:

Stainless steel, 300 series (SS300; refer to the certification drawings, provided in Appendix 1.3.1, AOS Transport Packaging System, Certification Drawings, for applicable national material specification)

Cask lid attachment bolts (ASME SB-637, UNS N07718)

Tungsten alloy (Tungsten ATI Densalloy SD180 per AMS-T-21014, Class 3)

Carbon steel (Carbon Steel Forging per ASME SA-105/ASTM A105)

Rigid, closed-cell, polyurethane foam (General Plastics, FR-3700 series foam)

Trunnion screws (ASME SA-193, Grade B6 UNS S41000)

The AOS Transport Packaging System has an impact limiter component consisting of rigid, closed-cell, polyurethane foam encased by a 300 series stainless steel (SS300) shell. This energy-absorbing and temperature insulation material is a General Plastics LAST-A-FOAM FR-3700 resin.a The impact limiters force-deflection data, for each AOS Transport Packaging System model, is provided in Subsection 2.7.1.

These curves are obtained by conducting a collapsed analysis with the LIBRA Finite Element code.

A complete description of the analytical procedure, as well as all testing and validation conducted to verify the procedure, are also provided in Subsection 2.7.1.

Table 2-9 lists the mechanical properties used for stainless steel analyses. Due to the variations in the 300 series stainless steel, the material properties used in the evaluations were chosen to be conservative.

Properties selected are those of lesser values among the material choices.

Table 2-10 lists the mechanical properties used for the cask lid attachment bolt analysis.

Table 2-11 lists the mechanical properties used for the tungsten alloy structural and shielding analyses.

Table 2-12 lists the mechanical properties used for the carbon steel shielding analysis.

Table 2-13 lists the mechanical properties used for the trunnion screw analysis.

Table 2-14 and Table 2-15 list the mechanical properties for the General Plastics LAST-A-FOAM FR-3700 series foam used in the current AOS Transport Packaging System design [2.13].

Selected material properties are also provided in Appendix 2.12.5, Selected Material Properties References.

a. FR-3700 resin is capable of producing foam with a variety of parameters, specified by contract, and verified by measurement during manufacturing.

2-30 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-9. Stainless Steel Mechanical Properties (Reference [2.5])

Temperature

(°F)

Module of Elasticitya, E

(106 psi)

a. Module of Elasticity, Material Group G, Table TM-1, page 671.

Poissons Ratio Coefficient of Thermal Expansionb,

(10-6 in/in/°F)

b. Coefficient of Thermal Expansion for Austenitic Stainless Steels (Group 3), Table TE-1, page 651.
Density,

(lbm/in3)

Ultimate Tensile

Stressc, Su (ksi) c.

Ultimate Tensile Stress, for SA-182, Grade F304, Table U, line 32, page 450.

Yield

Stressd, Sy (ksi)
d. Yield Stress for SA-182, Grade F304, Table Y-1, line 37, page 552.

Design Stress Intensitye, Sm (ksi)

e. Design Stress Intensity for SA-351, Grade CF8, Table 2A, line 26, page 312.

-20 to 100 28.3 0.30 8.6 0.29 70.0 30.0 20.0 150 8.8 26.7 200 27.6 8.9 66.3 25.0 20.0 250 9.1 23.6 300 27.0 9.2 61.8 22.4 20.0 400 26.5 9.5 59.7 20.7 18.7 500 25.8 9.7 59.2 19.4 17.4 600 25.3 9.8 59.2 18.4 16.4 650 9.9 59.2 18.0 16.1 700 24.8 10.0 59.2 17.6 16.0 750 10.0 59.0 17.2 15.5 800 24.1 10.1 58.6 16.9 15.1 850 10.1 57.9 16.5 900 23.5 10.2 56.8 16.2 950 10.3 55.4 15.9 1,000 22.8 10.3 53.6 15.5

Radioactive Material Transport Packaging System Safety Analysis Report 2-31 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-10. Cask Lid Attachment Bolt Mechanical Properties (Reference [2.5])

Temperature

(°F)

Module of Elasticitya, E

(106 psi)

a. Module of Elasticity, Material Group B Nickel Steel, Table TM-4, page 675, ASME Code,Section II, Part D - Properties (Reference [2.5]).

Poissons Ratio Coefficient of Thermal Expansionb,

(10-6 in/in/°F)

b. Coefficient of Thermal Expansion for Material N07718, Table TE-4, page 658, ASME Code,Section II, Part D - Properties (Reference [2.5]).
Density,

(lbm/in3)

Ultimate Tensile

Stressc, Su (ksi) c.

Ultimate Tensile Stress and Yield Stress calculated from the Stress Intensity values, provided in Table 4, Line 33, page 416, ASME Code,Section II, Part D - Properties (Reference [2.5]).

Yield

Stressc, Sy (ksi)

Design Stress Intensityd, Sm (ksi)

d. Stress Intensity values for Material N07718, provided in Table 4, Line 33, page 416, ASME Code,Section II, Part D - Properties (Reference [2.5]).

-100 29.9 0.31 0.297 70 29.0 7.0 185.0 150.0 50.0 200 28.3 7.2 177.6 144.0 48.0 300 27.8 7.3 173.5 140.7 46.9 400 27.6 7.5 170.6 138.3 46.1 500 27.1 7.6 168.7 136.8 45.6 600 26.8 7.7 166.8 135.3 45.1 700 26.4 7.8 165.8 134.4 44.8 800 25.8 7.9 164.3 133.2 44.0 (Su 70°F) = Su temp Sm temp Sm 70°F

2-32 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-11. Tungsten Alloy Material Mechanical Properties Module of Elasticitya, E

(106 psi)

a. Grade Specification Conformance Table, page 16 (Reference [2.15]).

Poissons Ratiob

b. Chapter 6, Table 6.1, page 274 (Reference [2.18]).

Coefficient of Thermal Expansionc,

(10-6 in/in/°F) c.

Reference [2.17]; = 4.6 x 10-6 in/in/°C

  • 5/9 = 2.5 x 10-6 in/in/°F.
Densitya,

(lbm/in3)

Yield Stressd, Sy (ksi)

d. Typical Densalloy Properties, page 7 (Reference [2.15]).

50.0 0.29 2.5 0.655 75.0 Table 2-12. Carbon Steel (SA-105) Material Mechanical Properties (Reference [2.5])

Temperature

(°F)

Module of Elasticitya, E

(106 psi)

a. Module of Elasticity, Carbon Steel with C 0.30%, Table TM-1, page 671 (Reference [2.5]).

Poissons Ratio Coefficient of Thermal Expansionb,

(10-6 in/in/°F)

b. Coefficient of Thermal Expansion for Carbon and Low Alloy Steel (Group 1), Table TE-1, page 648 (Reference [2.5]).
Density,

(lbm/in3)

Ultimate Tensile

Stressc, Su (ksi) c.

Ultimate Tensile Stress, for SA-105, Forging, Table U, line 23, page 424 (Reference [2.5]).

Yield

Stressd, Sy (ksi)
d. Yield Stress for SA-105, Forging, Table Y-1, line 26, page 500 (Reference [2.5]).

Design Stress Intensitye, Sm (ksi)

e. Design Stress Intensity for SA-105, Forging, Table 2A, line 35, page 260 (Reference [2.5]).

-100 30.2 0.30 0.283 70 29.5 6.4 70.0 36.0 23.3 200 28.8 6.7 70.0 33.0 21.9 250 6.8 70.0 32.4 300 28.3 6.9 70.0 31.8 21.3 400 27.7 7.1 70.0 30.8 20.6 500 27.3 7.3 70.0 29.3 19.4 600 26.7 7.4 70.0 27.6 17.8 650 7.5 70.0 26.7 17.4 700 25.5 7.6 70.0 25.8 17.3 750 7.7 69.1 24.9 800 24.2 7.8 64.3 24.1 850 7.9 58.6 23.4 900 22.4 7.9 52.3 22.8 950 8.0 45.9 22.1 1,000 20.4 8.1 40.4 21.4

Radioactive Material Transport Packaging System Safety Analysis Report 2-33 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

This SAR contains two sets of material properties for the FR-3700 foam materials. One set is presented in Table 2-14 and Table 2-15 [2.13], and the second set is presented in Appendix 2.12.5 [2.19]. The foam analyses, free drops, were performed using the properties values of the foam properties presented in Appendix 2.12.5. When the new data was published in 2005, AOS assessed the difference in the data between the two revisions of the document, and after consulting with the manufacturer, it was concluded not to revise the analytical work for the new values, but rather address this issue at the time of manufacturing and to provide verification by the testing program imposed by the purchase order. To ensure that the required crush strength limits are met during fabrication by the current foam formulation, AOS has reduced the prescribed foam density provided in Revision E of this SAR; therefore, instead of using foam densities of 20 pcf, 10 pcf, and 12 pcf for the Model AOS-025, AOS-050, and AOS-100, respectively, the new densities are 18 pcf, 8 pcf, and 11 pcf, respectively. In addition, AOS has assigned the values presented in Appendix 2.12.5 as the maximum value limits, which represent a tolerance of +15%. The current foam formulation [2.13] has a higher crush strength than the 2003 version [2.19] of the model.

Table 2-14 and Table 2-15 present the properties for the new density values.

Table 2-13. Trunnion Screw Mechanical Properties (Reference [2.5]) - All Models Model Screw Size /

ASME Standard Stress Area Minimum Tensile Strengtha

a. Table 4, line 26, page 413 (Reference [2.5]).

Yield Strengtha cm2 in2 kPa ksi kPa ksi AOS-025 1/4-28 UNF-2A /

ASME SA-193, Grade B6 UNS S41000 0.235 0.036 7.58E+05 110 5.86E+05 85 AOS-050 3/8-24 UNF-2A /

ASME SA-193, Grade B6 UNS S41000 0.566 0.088 7.58E+05 110 5.86E+05 85 AOS-100 3/4-16 UNF-2A /

ASME SA-193, Grade B6 UNS S41000 2.406 0.373 7.58E+05 110 5.86E+05 85

2-34 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-14. LAST-A-FOAM FR-3700 Series Foam Dynamic Strength, psi, Parallel to Direction of Rise - All Modelsa

a. Information provided in Reference [2.13].

AOS-025 (FR-3718 18-pcf. Foam)

Temp

(°F)

Strain (in./in.)

10%

20%

30%

40%

50%

60%

65%

70%

-20 2,215 2,077 2,112 2,268 2,647 3,418 4,258 4,694 75 1,624 1,558 1,603 1,730 2,026 2,640 3,334 3,761 100 1,390 1,355 1,412 1,522 1,805 2,380 3,004 3,653 140 1,157 1,151 1,204 1,297 1,523 2,016 2,540 3,073 180 991 979 1,044 1,123 1,322 1,729 2,142 2,599 220 892 869 917 985 1,140 1,440 1,810 2,194 260 630 619 661 725 837 1,151 1,445 1,824 AOS-050 (FR-3708 8-pcf. Foam)

Temp

(°F)

Strain (in./in.)

10%

20%

30%

40%

50%

60%

65%

70%

-20 465 472 464 455 496 615 776 892 75 357 346 352 353 394 483 603 660 100 309 305 314 314 355 440 549 634 140 258 259 268 271 308 378 477 558 180 229 228 237 240 273 330 411 475 220 214 207 212 215 242 287 357 411 260 157 152 163 165 190 239 297 353 AOS-100 (FR-3711 11-pcf. Foam)

Temp

(°F)

Strain (in./in.)

10%

20%

30%

40%

50%

60%

65%

70%

-20 851 797 798 814 929 1,169 1,525 1,633 75 624 598 606 621 711 904 1,194 1,308 100 534 520 534 546 633 815 1,076 1,271 140 444 442 455 465 535 690 910 1,069 180 381 375 395 403 464 591 767 904 220 343 333 346 353 400 493 648 763 260 242 238 250 260 294 394 517 634

Radioactive Material Transport Packaging System Safety Analysis Report 2-35 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-15. LAST-A-FOAM FR-3700 Series Foam Dynamic Strength, psi, Perpendicular to Direction of Rise - All Modelsa

a. Information provided in Reference [2.13].

AOS-025 (FR-3718 18-pcf. Foam)

Temp

(°F)

Strain (in./in.)

10%

20%

30%

40%

50%

60%

65%

70%

-20 2,183 2,063 2,097 2,283 2,617 3,372 4,104 4,347 75 1,614 1,548 1,591 1,715 2,018 2,646 3,316 3,739 100 1,348 1,314 1,369 1,509 1,758 2,333 2,922 3,380 140 1,149 1,127 1,179 1,302 1,517 2,020 2,527 2,983 180 985 972 1,021 1,113 1,317 1,732 2,164 2,547 220 838 817 862 942 1,095 1,443 1,801 2,145 260 610 600 640 701 834 1,074 1,338 1,628 AOS-050 (FR-3708 8-pcf. Foam)

Temp

(°F)

Strain (in./in.)

10%

20%

30%

40%

50%

60%

65%

70%

-20 470 452 449 456 504 633 800 892 75 353 334 335 345 383 478 599 664 100 298 290 295 307 345 436 545 613 140 262 257 262 273 303 379 474 536 180 219 220 229 238 265 336 415 472 220 205 196 202 210 231 289 355 407 260 155 150 158 165 185 232 289 329 AOS-100 (FR-3711 11-pcf. Foam)

Temp

(°F)

Strain (in./in.)

10%

20%

30%

40%

50%

60%

65%

70%

-20 832 781 783 811 912 1,148 1,497 1,515 75 615 586 594 609 703 901 1,210 1,304 100 514 497 512 536 612 795 1,066 1,178 140 438 427 441 463 529 688 922 1,040 180 375 368 381 396 459 590 790 888 220 319 309 322 335 382 492 657 748 260 233 227 239 249 290 366 488 568

2-36 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.2.2 Chemical, Galvanic, and/or Other Reactions Galvanic reaction occurs when two dissimilar metals with different potentials are in contact in the presence of an electrolyte. Removing or reducing these factors can decrease the possible interactions leading to a galvanic reaction. Avoiding joints using dissimilar metals, selecting joint materials that have lower potential differences, and/or eliminating the electrolyte can prevent galvanic interaction.

Table 2-16 lists the six (6) permanent dissimilar metal joints that are used within the cask component of the AOS Transport Packaging System. The joints described in Table 2-16 are shown in the certification drawings for each cask, listed in Table 1-5, AOS Transport Packaging System Certification Drawing List -

All Models.

The materials involved in joints 1, 2, 4, 5, and 6 are 300 series stainless steel and tungsten alloy or carbon steel. For joint 3, the materials are 300 series stainless steel and copper alloy. These joints are all located within the cask component of the AOS Transport Packaging System. The potential difference between stainless steel and tungsten alloy and stainless steel and copper is sufficiently low, as to not produce galvanic effects. (Refer to Reference [2.12] for potential difference information for these materials.) For the stainless steel and carbon steel joint, the carbon steel is electroless nickel-plated, with a minimum thickness of 21 microns (0.00083 in.) to reduce the different potentials.

Table 2-17 lists the four (4) temporary joints, where dissimilar metals are connected. In the case of these temporary joints, it can be said that their duration as a jointed unit, service life of their components, and continuous operational inspection preclude galvanic corrosion from occurring or going undetected.

Table 2-16. Permanent Dissimilar Metal Joints within Cask Component Joint Number Joint Description 1

Outside surfaces of the cask cavity shell, and shielding material inside diameter surfaces 2

Inside diameter surface of the cask outer shell, and outside diameter surface of the shielding material 3

Two (2) flat contact surfaces between the port and cask vent port plugs, and recessed cavity within the cask outer shell 4

Cask lid plug shell inside surface, and cask end plug 5

Cask cavity end outside recess inner surface, and cavity end plug 6

Bottom plate, and cask end plug Table 2-17. Temporary Dissimilar Metal Joints within Cask Component Joint Number Joint Description a

Cask lid closure joint b

Radioactive content against its holders c

Content holder against the shoring devices d

Content holder or shoring device against the cask cavity surfaces

Radioactive Material Transport Packaging System Safety Analysis Report 2-37 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

The casks fabrication process excludes any moisture (electrolyte) from being present within the cask.

During shipment (jointed unit), the cavity must be dry, regardless of how it was loaded. If the cavity was loaded in water, the cavity must be vacuum-dried. Following this procedure eliminates the presence of the electrolyte, one of the factors for galvanic interaction. Refer to Paragraph 7.1.3.1, Securing the Cask Lid, for the vacuum drying procedure.

Possible galvanic interaction is eliminated by controlling the potential difference for both permanent and temporary dissimilar metal joints, and by preventing the presence of an electrolyte, during fabrication and shipment.

2.2.3 Effects of Radiation on Materials The AOS Transport Packaging Systems cask component is comprised of the following construction materials:

300 series stainless steel (SS300), tungsten alloy or low carbon steel alloy for the cask body, cask lid, and cask lid plug components Nickel alloy for the cask lid attachment bolts Silver, nickel-chromium alloy, and stainless steel for the cask lid metallic seal Silicone material for the O-Rings used in the cask lid elastomeric seal and port cover Of all these materials, the one most affected by radiation is the silicone material. However, these port cover O-Ring components are replaced after each use, thus eliminating the cumulative effect of radiation.

The impact limiters are constructed of 300 series stainless steel and polyurethane foam materials. The effect of radiation upon the stainless steel material is minimal. Also, according the manufacturers data for the polyurethane foam (Reference [2.13]), its material does not incur any physical property changes when subjected to a maximum cumulative dose of 2 x 108 rads. Therefore, the impact limiters are not affected by radiation.

2-38 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.3 FABRICATION AND EXAMINATION 2.3.1 Fabrication This subsection describes the fabrication processes used for the AOS Transport Packaging System, such as fitting, aligning, welding and brazing, heat treatment, and foam pouring. Table 2-8 provides a breakdown of the AOS Transport Packaging System by category of functionally, the corresponding applicable Code and/or Standard, and the Safety Classification. The information provided in Table 2-8 follows the guidelines presented in NUREG/CR-3854, Fabrication Criteria for Shipping Containers, and NUREG/CR-3019, Recommended Welding Criteria For Use in the Fabrication of Shipping Containers for Radioactive Materials (References [2.24] and [2.25], respectively).

Table 2-18 lists the material selection specifications for the major components used in the AOS Transport Packaging System.

Radioactive Material Transport Packaging System Safety Analysis Report 2-39 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-18. Material Selection of Major AOS Transport Packaging System Components (Typical)

Component Material Selection First Alternate Material Second Alternate Material Certification Drawinga

a. The Model AOS-100A certification drawings are used for the Item No. (column) references for completeness of the table information.

Item No.

Cask Cask Outer Shell ASME SA-182/

ASTM A182, Grade F304 or F316 ASME SA-351/

ASTM A351, Grade CF 8 ASME SA-451/

ASTM A451, Grade CPF 8 105E9712 1

Cask Lid ASME SA-240/

ASTM A240, Type 304 or 316 ASME SA-182/

ASTM A182, Grade F304 or F316 2

Cask Cavity Shell ASME SA-182/

ASTM A182, Grade F304 or F316 ASME SA-351/

ASTM A351, Grade CF 8 ASME SA-451/

ASTM A451, Grade CPF 8 3

Shielding Material Tungsten ATI Densalloy SD180 per AMS-T-21014, Class 3 Carbon Steel Forging per ASME SA-105/

ASTM A105 4, 8, 12 Trunnion ASME SA-479/

ASTM A479, Type 304 or 316 5

Cask Lid Plug ASME SA-240/

ASTM A240, Type 304 or 316 ASME SA-182/

ASTM A182, Grade F304 or F316 6

Cover Plate ASME SA-240/

ASTM A240, Type 304 or 316 ASME SA-182/

ASTM A182, Grade F304 or F316 7

Cask Lid Attachment Bolts ASME SB-637, UNS N07718 15 Bottom Plate ASME SA-240/

ASTM A240, Type 304 or 316 ASME SA-182/

ASTM A182, Grade F304 or F316 16 Trunnion Screws ASME SA-193, Grade B6 UNS S41000 24 Port Plug ASME SA-182/

ASTM A182, Grade F304 or F316 ASME SA-479/

ASTM A479, Type 304 or 316 32 Impact Limiter Shell and Ribs ASME SA-240/

ASTM A240, Type 304 or 316 105E9713 1 - 11 Foam Polyurethane Foam (General Plastics FR-3700 Series Foams) 12

2-40 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.3.1.1 Materials Materials are procured by the Fabricator from material manufacturers or suppliers that have been audited and approved by the Fabricator, under their approved Quality Plan.

Materials are in accordance with the applicable rules of ASME Section II Parts A, B, and C, as applicable; ASME Section III NCA-3800; Heat treatment of new material is controlled by the material procurement procedure and Quality Plan.

Material purchased requiring upgrading (ASME) or commercial grade dedication uses procedures and/or checklists approved in accordance with the Fabricators approved Quality Plan.

Material certification is approved prior to final acceptance of the material.

Deviations and non-conformances relating to the material are dispositioned by a written procedure as specified in the Fabricators Quality Plan, prior to material acceptance.

2.3.1.2 Fabrication Fabrication is conducted by the Fabricator, in accordance with established, written process documentation (travelers, bills of material, weld maps, inspection and test reports), and using written procedures for processes.

Process documentation provides for the identification and control of all materials to be used in the fabrication process of components and assembly. Material is identified and recorded on the appropriate process documents. The process documentation provides for hold points, to allow for critical verifications by the purchaser.

2.3.1.3 Forming Forming has limited use in the fabrication of the AOS Transport Packaging System. It may be used in producing the impact limiter heads and shells.

2.3.1.4 Machining Forgings, plates, and round bars (purchased in the stock-on condition) are machined to established dimensional configurations, as identified on the drawings, and delineated by the Fabricators process documentation. The dimensional configurations established allow for fitting and alignment of the components that are part of components, sub-assemblies, and assemblies.

Welded components are final machined to established dimensional configurations, as identified on the drawings, and delineated by the Fabricators process documentation.

Those components that are not a part of the assembly (cask lid, trunnions, and trunnion details) are machined to final configuration as identified on the drawings, and delineated by the Fabricators process documentation.

Radioactive Material Transport Packaging System Safety Analysis Report 2-41 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.3.1.5 Fitting and Assembling Components of the AOS Transport Packaging System are fitted and assembled in accordance with the Fabricators process documentation. Recording of the completion of work is maintained in the process documents.

Alignment of sections to be joined by welding is controlled in accordance with the Fabricators process documentation and the applicable drawings.

2.3.1.6 Welding These welding processes can be used in the fabrication of the AOS Transport Packaging System - Shielded Metal Arc Welding (SMAW), Flux Cored Arc Welding (FCAW), Gas Tungsten Arc Welding (GTAW), Gas Metal Arc Welding (GMAW) Submerged Arc Welding (SAW) or Plasma-Transferred Arc Welding (PTAW). Additional American Welding Society (AWS) welding processes can also be used.

Welding Procedure Specifications (WPSs) are in accordance with ASME Section IX requirements, and supplemented as required by ASME Section III NF/NG-4330.

Qualified welders assigned by the Fabricator must conduct all welding activities.

Welder Qualification records are in accordance with ASME B&PV Code Section III NF/NG-4320, and are on file at the Fabricators location.

2.3.1.7 Heat Treating There are no heat treating requirements for the AOS Transport Packaging System, with the exception of heat treatment conducted, where required, by applicable material specifications.

2-42 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.3.2 Examination Table 2-19 summarizes the AOS Transport Packaging System examination program. Additional detailed information is provided in Chapter 8, Acceptance Tests and Maintenance Program.

Table 2-19. Examination Program Summary Test Category Test Type Reference Test Description Materials Stainless Steel Certified Material Test Report ASME Code,Section II, Part A, and applicable requirements of NX-2500,Section III.

Series of chemical and mechanical tests to determine conformance with material specification.

Tungsten Alloy Density Verification Straight Beam method per NG-2532.1,Section III, Division 1, 2001 Edition with 2003 Addendum.

One UT examination of the material surfaces and calculating the resulting component density by weighing and dimensionally inspecting the component, to determine its volume.

Foam Formulation Verification Table 8-5, LAST-A-FOAM FR-3700 Series Foams - Testing Program.

Series of tests to establish the material characteristics baseline.

Fabrication Component Adherence to Drawing Certification Drawings. Refer to Table 1-5, AOS Transport Packaging System Certification Drawing List - All Models.

Visual and Dimensional inspections.

Sub-assembly Assembly Pressure and Containment ASME Code,Section V, and applicable requirements of NB-6112,Section III, and ANSI N14.5, Section 7.3.

Pneumatic and Leakage test, per Reference [2.11].

Weldment NDE ASME Code,Section V, and applicable requirements of NX-5000,Section III.

Visual, Penetrant, and Ultrasonic tests (VT, PT, and UT, respectively).

Radioactive Material Transport Packaging System Safety Analysis Report 2-43 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.4 GENERAL REQUIREMENTS FOR ALL PACKAGES 2.4.1 Minimum Package Size All AOS Transport Packaging System model dimensions are greater than 10 cm (4 in.), and therefore exceed minimum package size requirements.

2.4.2 Tamper-Indicating Feature A tamper-indication feature, installed across the impact limiter joint section, provides evidence of unauthorized tampering. With the package assembled for transportation and the impact limiter installed, there are no additional covers, ports, nor other accesses that must be closed during Normal conditions of transport. Refer to Paragraph 7.1.3.4, Preparing the Cask for Transport of Radioactive Material, for further details.

2.4.3 Positive Closure The AOS Transport Packaging System models are used for shipping radioactive materials within the cask component. The first level of closure of the cask cavity is provided by the cask lid seal joint. The cask cavity shell consists of two SS300 series forgings, machined to form and joined together by a full-penetration weld. The cask lid seal joint consists of the cask lid, a cask lid seal, and a series of cask lid attachment bolts. The bolts are tightened to a prescribed torque value. There are two (2) other penetration points into the cavity. The port plugs are threaded into the cask cavity and welded onto the outside to the cask outer shell. Copper seals, located at both ends of the port plugs, ensure the leak tightness of these joints. The port plug conduits are closed and sealed by pipe plugs and straight thread caps with silicone O-Rings.

2-44 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5 LIFTING AND TIE-DOWN STANDARDS FOR ALL PACKAGES The following information is presented:

Lifting Devices Tie-Down Devices Other Devices 2.5.1 Lifting Devices 10 CFR 71.45(a) [2.1] requires that lifting devices that are a structural part of the transport package must be capable of supporting three times the weight (3 W) of the loaded package, without generating stress in any material of the package in excess of its yield stress.

Figure 2-13 presents a cross-section of the trunnion area, as well as the force diagram associated with the lifting loads. The dimensions for the figure are listed in Table 2-20.

Figure 2-13. Trunnion Area Cross-Section and Force Diagram Associated with Lifting Loads KEENSERT

Radioactive Material Transport Packaging System Safety Analysis Report 2-45 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.1.1 Cask Lifting Analysis - Trunnion Bolting Evaluation The vertical force, FV, applied to each trunnion is defined as:

FV

=

(DLF

  • 1.0
  • package weight) / 2 where:

DLF

=

Dynamic Load Factor, 1.2 The horizontal force, Fh, is located at the bottom of the trunnion, and is defined as:

FH

=

FV

  • tan30° The effects of forces FV and FH are transferred from their location at the bottom of the trunnion to the bolt centroid, located within the interface of the trunnion and cask. The trunnion design is made such that the vertical force, FV, is reacted to by the cask in bearing and does not load the bolts in shear.

Moment about the bolt centroid x-axis is:

Mx

=

FV * (B + C + L/2) + FH

  • E/2 Tensile force in the bolt furthest away from the bolt centroid about the x-axis due to moment, and assumes each bolt area is equal to 1.0:

Fb

=

(Mx

  • CL) / Ix-x where:

Ix-x

=

(ry)2

2-46 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Tensile force in each bolt due to horizontal force is:

Ft

=

FH / 6 The resulting load on the bolt is (from Reference [2.28]):

FB

=

( kb / (kb + km) )

  • P + Fpreload where:

kb

=

Bolt stiffness

=

  • D2 nominal
  • Ebolt / (4
  • l) km

=

Member stiffness

=

2 *

  • D2 nominal
  • Emember / l P

=

Maximum total load on the bolted assembly =

Fb + Ft Fpreload =

Pre-torque / (0.2

  • Dnominal)

Maximum total bolt tensile stress is:

ST

=

Fb / Atensile Factor of safety is defined as:

FS

=

Sy / ST

Radioactive Material Transport Packaging System Safety Analysis Report 2-47 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-20. Lifting Load Analysis - All Models Item Units Model AOS-025 AOS-050 AOS-100 Metric English Metric English Metric English Weight kg lbs.

76 168 536 1,181 4,314 9,510 A

cm in.

4.14 1.63 8.26 3.25 16.51 6.50 B

cm in.

0.84 0.33 1.65 0.65 3.30 1.30 C

cm in.

0.19 0.08 0.41 0.16 0.84 0.33 D

cm in.

1.65 0.65 3.30 1.30 6.60 2.60 E

cm in.

1.91 0.75 3.81 1.50 7.65 3.01 L

cm in.

0.71 0.28 1.45 0.57 2.69 1.06 1/2L cm in.

0.36 0.14 0.72 0.29 1.35 0.53 FT N

lbf.

518 116 3,640 818 29,308 6,589 FH N

lbf.

259 58 1,820 409 14,654 3,294 FV N

lbf.

448 101 3,152 709 25,382 5,706 Bolt Size 1/4-28 UNF - 2A x 0.5L 3/8 - 24 UNF - 2A x 0.75L 3/4 - 16 UNF-2A x 1.50L Material SA 193 Grade B6 SA 193 Grade B6 SA 193 Grade B6 Pre-Torque Nm lbf-ft.

5.42 4

16.27 12 135.58 100 Bolt Circle cm in.

2.90 1.14 5.77 2.27 10.80 4.25 Su MPa ksi 758 110 758 110 758 110 Sy Pa psi 5.86E+08 8.50E+04 5.86E+08 8.50E+04 5.86E+08 8.50E+04 Quantity 6

6 6

Keensert KNH 428J KNH 624J KNH 1216J 1/4-28 UNF - 3B x 0.37 3/8-24 UNF - 3B x 0.50 3/4-16 UNF - 3B x 1.12 Dnominal cm in.

0.64 0.25 0.95 0.38 1.91 0.75 Atensile cm2 in2 0.23 0.036 0.57 0.088 2.41 0.373 Mx Nm lbf-in.

9 77 122 1,083 1,953 17,283 CL cm in.

1.25 0.49 2.50 0.98 4.67 1.84 Ix-x per unit area a

cm2 in2 6.29E+00 9.75E-01 2.49E+01 3.86E+00 8.74E+01 1.35E+01 Fb N

lbf.

1.73E+02 3.89E+01 1.22E+03 2.75E+02 1.04E+04 2.35E+03 Ft N

lbf.

4.31E+01 9.70E+00 3.03E+02 6.82E+01 2.44E+03 5.49E+02 Ebolt Pa psi 2.01E+11 2.92E+07 2.01E+11 2.92E+07 2.01E+11 2.92E+07 Emember Pa psi 1.95E+11 2.83E+07 1.95E+11 2.83E+07 1.95E+11 2.83E+07 I

cm in.

9.40E-01 3.70E-01 1.27E+00 5.00E-01 2.84E+00 1.12E+00 kb N/m lbf/in.

6.78E+08 3.87E+06 1.13E+09 6.45E+06 2.02E+09 1.15E+07 km N/m lbf/in.

5.26E+09 3.00E+07 8.76E+09 5.00E+07 1.56E+10 8.93E+07 kb / (kb + km) 1.14E-01 1.14E-01 1.14E-01 1.14E-01 1.14E-01 1.14E-01

2-48 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Typically in a bolting joint design, a preload torque is assigned to the bolt(s). This is to ensure that the joint will have the capability to react to the applied working load. Therefore, the working load in the bolt must be within the magnitude of, or less than, the resultant load from the preload. In the analysis presented in Table 2-20, the resultant bolt load due to the preload (Fpreload) is 8.00E+03 lbf., while the working load is 330 lbf.a Hence, the preload value of 100 lbf-ft is an adequate value applied to the Model AOS-100 trunnion design. In addition to applying a preload, the bolts are coated with anti-vibration compound prior to installation, to enhance the bolted joints efficiency.

P N

lbf.

2.16E+02 4.86E+01 1.53E+03 3.44E+02 1.29E+04 2.90E+03 Fpreload N

lbf.

4.27E+03 9.60E+02 8.54E+03 1.92E+03 3.56E+04 8.00E+03 FB N

lbf.

4.29E+03 9.66E+02 8.72E+03 1.96E+03 3.71E+04 8.33E+03 ST Pa psi 1.83E+08 2.65E+04 1.54E+08 2.23E+04 1.54E+08 2.23E+04 FS = Sy / ST 3.20 3.20 3.81 3.81 3.81 3.81

a. This method is shown in Equation 6-25, Section 6.12 of Reference [2.28].
a. The working load value of 330 lbf. is obtained by subtracting the preload force (Fpreload) value of 8.00E+03 lbf.

from the total force (Fb) of 8.33E+03 lbf [2.28].

Table 2-20. Lifting Load Analysis - All Models (Continued)

Item Units Model AOS-025 AOS-050 AOS-100 Metric English Metric English Metric English

Radioactive Material Transport Packaging System Safety Analysis Report 2-49 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.1.2 Cask Socket Bearing Stress Check The bearing area, as illustrated in Figure 2-13, is:

Area =

A

  • B where:

A and B are provided in Table 2-20.

The ultimate stress for the cask material is 70 ksi.

Margin of safety is defined as:

MS

=

(Su / St) - 1.0 Table 2-21 lists the average bearing stress.

Table 2-21. Average Bearing Stress - All Models Model Force, FV (lbf.)

Area (in2)

Stress (psi)

Margin AOS-025 101 0.54 559 124.2 AOS-050 709 2.11 1,008 68.4 AOS-100 5,706 8.45 2,026 33.6

2-50 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.1.3 Shear Stress at Trunnion Neck The maximum shear stress for a circular section is:

SV = (4

  • A)

Yield stress in shear is 0.58 times the tensile yield stress. Then, Sy = 17.4 ksi.

Margin of safety is defined as:

MS

=

(Sy / St) - 1.0 Table 2-22 lists the maximum shear stresses.

Lifting device margins of safety, in all transport package models, are greater than 3.0. The neck of the trunnion has the lowest margin of safety. Should failure occur in the trunnion neck, no damage to the transport package will occur.

Table 2-22. Maximum Shear Stress, SV - All Models Model Force, FV (lbf.)

Area (in2)

Stress (psi)

Margin AOS-025 101 0.33 1,220 13.26 AOS-050 709 1.33 2,131 7.17 AOS-100 5,706 5.31 4,298 3.05

Radioactive Material Transport Packaging System Safety Analysis Report 2-51 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.2 Tie-Down Devices The transport package contents and shield material are sealed within the cask. The cask is placed within the impact limiter, which is then placed upon the tie-down hardware. (Refer to Figure 1-1 through Figure 1-4 for an isometric view of each transport package model.)

10 CFR 71.45(b) [2.1] requires that, if there is a system of tie-down devices that is a structural part of the transport package, the system must be capable of withstanding a static force applied to the center of gravity of the package with the following:

1.

Vertical component of two times the weight (2 W) of the package and its contents; 2.

Horizontal component along the direction of travel of ten times the weight (10 W) of the package and its contents; and 3.

Horizontal component in the transverse direction of five times the weight (5 W) of the package and its contents.

These applied loads do not generate stresses in any package material in excess of the yield strength of that material, as discussed in the following tables:

Table 2-217, Load Case 221, Forward 10g Vibration Inertia Load, Normal Conditions of Transport - Models AOS-100A and AOS-100A-S Table 2-218, Load Case 222, Lateral 5g Vibration Inertia Load, Normal Conditions of Transport - Models AOS-100A and AOS-100A-S Table 2-219, Load Case 223, Vertical 2g Vibration Inertia Load, Normal Conditions of Transport - Models AOS-100A and AOS-100A-S Detailed analyses of tie-down devices are presented in Appendix 2.12.12.

2.5.3 Other Devices The following information demonstrates the analysis of other individual devices, and demonstrates conformance to or with 10 CFR 71.45(b) [2.1]:

Analyses of Shipping Cage and Shipping Cage Fasteners Stress Analysis of Shipping Cages Analysis of Shipping Cage Fasteners - Model AOS-025 Analysis of Shipping Cage Fasteners - Model AOS-050 Analysis of Shipping Cage Fasteners - Model AOS-100 Analysis of Impact Limiter Mechanical Connectors Analyses of Shielding Devices Stress Analysis of Cavity Liner - Model AOS-025

2-52 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.3.1 Analyses of Shipping Cage and Shipping Cage Fasteners 2.5.3.1.1 Stress Analysis of Shipping Cages The combination of shipping cage wire mesh panels and angle x-section frame behaves as a Tension Field Beam. In Tension Field Beams, web panels are assumed to buckle upon load application, and shear forces, V, are transmitted by web tension stress, t [2.9]. The wire mesh behaves as an ideal Tension Field web panel, because wire mesh can transmit only tension stress. Panel dimensions used in the analysis are larger than actual dimensions, to accommodate possible changes. Use of larger panel dimensions is conservative. Additionally, the shipping cage design used in the evaluation is a more simple design that the actual design, making the analysis conservative.

Figure 2-14. Mesh Diagonal Tension The web thickness equivalent to the wire mesh is determined using Reference [2.10]. For the AOS Transport Packaging System, the shipping cage mesh size corresponds, approximately, to the 22 x 60 mm steel mesh in Reference [2.10]. From Reference [2.10], this mesh weight is:

w = 3.69 kg/m2 = 0.00525 lb/in2 The equivalent web thickness for steel with density = 0.28 lb/in3 is then:

tW = w / = 0.00525 / 0.28 = 0.019 in.

From Reference [2.9], with ft and fs web tension and shear stress resultants, and the web diagonal tension angle:

ft = 2

  • fs / sin 2

= 45° ft = 2

  • fs

Radioactive Material Transport Packaging System Safety Analysis Report 2-53 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Web strain energy due to tension stress, t, is:

U = (1/2) (t)2 (Aw

  • tw) / E where:

Aw

=

Web area tw

=

Web thickness For square panels with side length L, and shear force V:

A = L2 t = ft / tw = 2fs / tw fs = V / L U = 2V2 / E

  • tw The maximum displacement,, is provided by:

= U / V = 4 V / E

  • tw For the equivalent web, E = 107 psi, and tw = 0.019 inches.

Assuming shear force on each of two webs equals half (1/2) the total weight, W, under a 10 g acceleration:

V = 10 W / 2 = 5 W The maximum axial stress in the frame members is:

F = V

  • L = V / AF where, for the frame angles:

AF

=

1.5

  • 1.5
  • 0.19 = 0.4275 in2

=

Maximum shipping cage displacement t

=

Web diagonal tension stress F

=

Frame axial stress MS

=

Margin of safety, Fy / - 1, Fy = 20 ksi Calculated values for the shipping cage margins of safety are presented in Table 2-23, by model.

Table 2-23. Calculation of Shipping Cage Margins of Safety - All Models Model V

(lb.)

(in.)

L (in.)

t (ksi)

F (ksi)

MS AOS-025 144 0.030 18.0 0.84 0.34

> 10 AOS-050 696 0.147 36.0 2.04 1.63 8.8 AOS-100 2,169 0.457 72.0 3.17 5.07 2.9

2-54 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.3.1.2 Analysis of Shipping Cage Fasteners - Model AOS-025 The Model AOS-025 shipping cage sits on top of the transport pallet with screws that pass vertically through flanges on four (4) sides of the shipping cage. There are three (3) screws on each side of the shipping cage and one (1) each on its front and back (total of eight (8)). The shipping cage is made with five (5) frames covered with expandable metal screens. The frames are made with 1.5 in. x 1.5 in.

aluminum angles with a thickness of 0.19 in. The actual shipping cage dimensions are used in the analysis. The shipping cage is 15 in. long by 15 in. wide by 18 in. high. Fastener properties are in accordance with ASME SA-193/ASTM A193, GRADE B6 (UNS S41000), -or-an alternate material, ASTM A193 Grade B8S (Nitronic 60). The calculations use the lesser yield strength of the two (2) materials.

Shipping Cage Mass Vertical Frame w = Density of aluminum = 0.1 lb/in3 W1 = 2 * (18 + 15) * (1.5 + 1.5)

  • 0.19
  • 0.1 = 3.8 lbs.

H1 = 9 in.

Top Frame W2 = 4

  • 15 * (1.5 + 1.5)
  • 0.19
  • 0.1 = 3.4 lbs.

H2 = 18 in.

Vertical Screen w = Unit weight of screen = 2.0 lb/ft2 W3 = 15/12

  • 18/12
  • 2.0 = 3.8 lbs.

H3 = H1 = 9 in.

Top Screen W4 = 15/12

  • 15/12
  • 2.0 = 3.1 lbs.

H4 = H2 = 18 in.

Maximum Inertia Force G = 10.0g Total Weight of Shipping Cage W = 4W1 +W2 + 4W3 + W4 = 36.9 lbs.

18" 15" 15"

Radioactive Material Transport Packaging System Safety Analysis Report 2-55 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Fastener Properties 3/8-16 UNC screws, quantity of eight (8), per ASME SA-193/ASTM A193, GRADE B6 -or-NITRONIC 60 PER ASME SA-193/ASTM A193, GRADE B8S (UNS S21800)

As = Stress Area = 0.0775 in2 Fy = 85 ksi (UNS S41000)

-or-Fy = 50 ksi (evaluate Nitronic 60 as an optional material)

Yield Stress in shear = Sy = 0.58

  • Fy = 29 ksi Fastener Shear Stress

= (G

  • W) / (8
  • As) = (10
  • 36.9) / (8
  • 0.0775) = 595.2 psi Fastener Axial Stress Shipping cages tipping moment is assumed to be resisted by three (3) screws along the back edge.

M = Tipping Moment = (G * (4W1 + 4W3)

  • H1) + (G * (W2 + W4)
  • H2) = 3,906 in-lb L = Moment Arm = 15 + 2
  • 1.5 - 0.69 = 17.3 in.

= M / (L

  • 3
  • As) = 971.1 psi Equivalent Stress e = (2 + 32) = 1,416.3 psi Margin of Safety MS = Fy / e - 1 = 29,000 / 1,416.3 - 1 = 19.5

2-56 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.3.1.3 Analysis of Shipping Cage Fasteners - Model AOS-050 The Model AOS-050 shipping cage has the same geometry as the Model AOS-025 shipping cage, but is 32.75 in. long by 32.75 in. wide by 33.25 in. high.

Shipping Cage Mass Vertical Frame w = Density of aluminum = 0.1 lb/in3 W1 = 2 * (32.75 + 33.25) * (1.5 + 1.5)

  • 0.19
  • 0.1 = 7.5 lbs.

H1 = 16.6 in.

Top Frame W2 = 4

  • 32.75 * (1.5 + 1.5)
  • 0.19
  • 0.1 = 7.5 lbs.

H2 = 33.25 in.

Vertical Screen w = Unit weight of screen = 2.0 lb/ft2 W3 = 32.75/12

  • 33.25/12 *2.0 = 15.1 lbs.

H3 = H1 = 16.6 in.

Top Screen W4 = 32.75/12

  • 32.75/12 *2.0 = 14.9 lbs.

H4 = H2 = 33.25 in.

Optional Shipping Cage Lifting Bar The Lifting Bar is made from a T-section 2 in. by 2 in. by 0.25 inch thick.

W5 = 32.75 * (2.0 + 2.0)

  • 0.25
  • 0.1 = 3.3 lbs.

H5 = H2 = 33.25 in.

Total Weight of Shipping Cage W = 4W1 +W2 + 4W3 + W4 + W5 = 116.2 lbs.

Maximum Inertia Force G = 10.0g 33.25" 32.75" 32.75"

Radioactive Material Transport Packaging System Safety Analysis Report 2-57 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Fastener Properties 3/8-16 UNC screws, quantity of eight (8), per ASME SA-193/ASTM A193, GRADE B6 -or-NITRONIC 60 PER ASME SA-193/ASTM A193, GRADE B8S (UNS S21800)

As = Stress Area = 0.0775 in2 Fy = 85 ksi (UNS S41000)

-or-Fy = 50 ksi (evaluate Nitronic 60 as an optional material)

Yield Stress in shear = Sy = 0.58

  • Fy = 29 ksi Fastener Shear Stress

= (G

  • W) / (8
  • As) = (10
  • 116.2) / (8
  • 0.0775) = 1874.2 psi Fastener Axial Stress Shipping cages tipping moment is assumed to be resisted by three (3) screws along the back edge.

M = Tipping Moment = (G

  • 4* (W1 + W3)
  • H1) + (G * (W2 + W4)
  • H2) +

(G

  • W5
  • H5) = 23,551.6 in-lb L = Moment Arm = 32.75 + 2 x 1.5 - 0.69 = 35.06 in.

= M / (L

  • 3
  • As) = 2,889.3 psi Equivalent Stress e = (2 + 32) = 4,345.8 psi Margin of Safety MS = Fy / e - 1 = 29,000 / 4,345.8 - 1 = 5.7

2-58 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.3.1.4 Analysis of Shipping Cage Fasteners - Model AOS-100 The Model AOS-100 shipping cage configuration is different from that of the Model AOS-025 and AOS-050 shipping cages. The shipping cage has vertical flanges that straddle the transport pallet, and the screws pass horizontally through the flanges. Because the transport pallet is captured within these flanges, the screws do not resist forward or sideways movement of the shipping cage. The screws only need to resist tipping of the shipping cage. The relevant parameters and calculations are provided below.

Shipping Cage Center of Gravity H1 = 46.6 in.

Shipping Cage Mass W = 450 lbs.

Shipping Cage Length L = 61.02 in.

Acceleration G = 10.0g Fastener Properties and Stress 1/2-13 UNC screws, quantity of 16, per ASME SA-193/ASTM A193, GRADE B6 -or-NITRONIC 60 PER ASME SA-193/ASTM A193, GRADE B8S (UNS S21800)

A = Tensile Stress Area = 0.142 in2 The 10.0-g acceleration tends to tip the shipping cage about one edge.

M = Tipping Moment = W

  • G
  • H1 = 450
  • 10
  • 46.6 = 209,700 in-lb Shipping cages tipping is conservatively assumed to be resisted by only four (4) screws in shear.

Total force on the screws is:

F = M / L = 209,700 / 61.02 = 3,436.6 lbs.

The shear stress in each screw is:

= F / 4As = 3,436.6 / (4

  • 0.142) = 6,050.3 psi Margin of Safety MS = Fy / - 1 = 29,000 / 6,050.3 - 1 = 3.8 61.02" 61.02" 67.4"

Radioactive Material Transport Packaging System Safety Analysis Report 2-59 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.3.2 Analysis of Impact Limiter Mechanical Connectors Maximum stress in the impact limiter mechanical connectors occurs under a Side Drop. Configuration of forces in a Side Drop are illustrated in Figure 2-15, where P is the impact force due to a 30-ft. drop. The mechanical connectors are loaded by the moment produced by the couple forces, P/2, and the offset distance, d.

While the impact load, P, is known, the offset distance, d, is indeterminate and depends upon the stiffness of the cask and impact limiter. The connector force is evaluated by an FEA analysis that takes cask and impact limiter stiffness into account. A displacement pattern simulating deformation due to a Side Drop is applied to the impact limiter, and reacted by fixing the cask. The maximum stressed mechanical connector and attached rib are included in the model, and the force in the connector is determined by the analysis.

Figure 2-15. Side Drop Impact Forces Connector Mechanical Connector Impact Limiter d

P/2 P/2 P

Cask Impact Limiter

2-60 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.3.2.1 Description of FEA Models The Model AOS-100 cask and impact limiter FEA model used in the analysis is illustrated in Figure 2-16. The FEA model contains 18,026 nodes and 18,281 elements, comprising 54,276 degrees of freedom (DOF). The foam stiffness used in the analysis is approximately the average foam stiffness value determined in the 30-ft. drop analysis. The impact loading due to the 30-ft. Side drop is applied by applying displacements to the impact limiter and fixing the top of the cask. The location of the applied displacements and fixed nodes are illustrated in Figure 2-17. A check of the total reaction forces at the casks fixed nodes is made, to ensure that sufficient loading is applied. A single mechanical connector and rib are modeled in the position that produces maximum stress. The connector is modeled as a spring element, and the spring force is found from the stress post-processor. FEA models for the Model AOS-025 and AOS-050 transport packages are scaled from the Model AOS-100 transport package, by a factor of 0.25 and 0.50, respectively.

LIBRA input data that defines the Side drop deformation is generated by the Fortran program, GENERATOR. This program uses the FEA model nodal data to search out the displaced nodes, and generates boundary condition records for these nodes. GENERATOR includes a SCALE parameter that accounts for the scaled Model AOS-025 and AOS-050 FEA models.

Radioactive Material Transport Packaging System Safety Analysis Report 2-61 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-16. Cask and Impact Limiter FEA Model - Model AOS-100 Figure 2-17. Cask and Impact Limiter Deformed FEA Model - Model AOS-100 Steel Cask Rib Mechanical Connector Foam Impact Limiter Applied Deformation Fixed Cask Nodes

2-62 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.3.2.2 Applied Force Check - Model AOS-025 The total force due to the applied displacements is the sum of y-direction (DOF_2) reaction forces at the 11 fixed cask nodes. The fixed cask node numbers start at 1978 and increase sequentially by 150. The force summation is provided in Table 2-24.

In Load Case 305 of the SAR, the maximum side impact loading is 1.80 x 105 lbs. Thus, the applied loading of 1.861 x 106 lbs. is conservative.

Table 2-24. Boundary Forces - Model AOS-025 NODE DOF_1 DOF_2 DOF_3 1978 -5.0006E-02 -2.4066E+04 -3.4473E-02 2128 2.4348E-03 -2.0315E+04 4.3499E-04 2278 -1.1101E-02 -1.6074E+04 -1.0881E-02 2428 4.7964E-03 -1.3833E+04 1.3197E-02 2578 -2.0154E-02 -1.2640E+04 -1.2181E-02 2728 -2.6443E-02 -1.2268E+04 8.6025E-03 2878 8.6144E-02 -1.2641E+04 -5.9291E-03 3028 4.3648E-02 -1.3837E+04 -2.1374E-02 3178 5.0801E-02 -1.6080E+04 2.2134E-02 3328 1.5450E-02 -2.0326E+04 -8.3435E-03 3478 5.2142E-03 -2.4082E+04 -2.0837E-02

= -1.861 x 105 2.5.3.2.3 Mechanical Connector Force - Model AOS-025 From the LIBRA stress post-processor, the force in the mechanical connector is:

F(025)

=

306.4 lbs.

Radioactive Material Transport Packaging System Safety Analysis Report 2-63 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.3.2.4 Applied Force Check - Model AOS-050 The total force due to the applied displacements is the sum of y-direction (DOF_2) reaction forces at the 11 fixed cask nodes. The fixed cask node numbers start at 1978 and increase sequentially by 150. The force summation is provided in Table 2-25.

In Load Case 305 of the SAR, the maximum side impact loading is 3.30 x 105 lbs. Thus, the applied loading of 3.74 x 106 lbs. is conservative.

Table 2-25. Boundary Forces - Model AOS-050 NODE DOF_1 DOF_2 DOF_3 1978 -3.5198E-02 -4.8342E+04 -2.7608E-02 2128 1.5677E-02 -4.0804E+04 5.3950E-03 2278 7.9958E-03 -3.2282E+04 -5.5868E-03 2428 2.7825E-02 -2.7781E+04 8.8376E-03 2578 8.2703E-03 -2.5383E+04 3.4030E-04 2728 -4.5529E-02 -2.4638E+04 1.9109E-02 2878 9.0454E-02 -2.5389E+04 -1.3850E-02 3028 4.1124E-02 -2.7793E+04 -1.7814E-02 3178 1.9868E-02 -3.2303E+04 1.7507E-02 3328 -2.8472E-03 -4.0837E+04 -4.7354E-03 3478 -5.0954E-03 -4.8386E+04 -1.6034E-02

= -3.738 x 105 2.5.3.2.5 Mechanical Connector Force - Model AOS-050 From the LIBRA stress post-processor, the force in the mechanical connector is:

F(050)

=

598.5 lbs.

2-64 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.3.2.6 Applied Force Check - Model AOS-100 The total force due to the applied displacements is the sum of y-direction (DOF_2) reaction forces at the 11 fixed cask nodes. The fixed cask node numbers start at 1978 and increase sequentially by 150.

The force summation is provided in Table 2-26.

In Load Case 305 of the SAR, the maximum side impact loading is 1.36 x 106 lbs. Thus, the applied loading of 1.50 x 106 lbs. is conservative.

Table 2-26. Boundary Forces - Model AOS-100 NODE DOF_1 DOF_2 DOF_3 1978 -3.7453E-02 -1.9344E+05 -2.8953E-02 2128 -2.6102E-02 -1.6327E+05 -9.0397E-03 2278 1.5500E-02 -1.2917E+05 -9.9378E-04 2428 1.8349E-02 -1.1116E+05 -1.8342E-02 2578 2.2709E-02 -1.0156E+05 1.6758E-02 2728 -5.7000E-02 -9.8571E+04 -3.3229E-02 2878 3.0340E-02 -1.0157E+05 -2.4999E-03 3028 6.9976E-03 -1.1118E+05 -3.9185E-02 3178 -2.1879E-02 -1.2922E+05 -3.7539E-02 3328 1.4692E-02 -1.6335E+05 -1.7748E-02 3478 4.3024E-02 -1.9354E+05 -1.2194E-02

= -1.50 x 106 2.5.3.2.7 Mechanical Connector Force - Model AOS-100 From the LIBRA stress post-processor, the force in the mechanical connector is:

F(100)

=

2.37 k

Radioactive Material Transport Packaging System Safety Analysis Report 2-65 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.3.2.8 Side Impact Load Summary Table 2-27 summarizes the mechanical connector side impact loads, by model.

2.5.3.2.9 Mechanical Connector Stress Analysis Two loading conditions are considered in the mechanical connector stress analyses:

Connector impact loads due to side impact 10g impact limiter mass inertia load Table 2-28 lists the 10g inertia loads, with connector load, P, provided by:

P

=

(10

  • W) / 8 where:

W

=

Weight of a single impact limiter Inertial force

=

10g Connectors

=

Eight (8) mechanical connectors A comparison of Table 2-27 and Table 2-28 shows that the side impact loadings summarized in Table 2-27 produce maximum connector load, for all three (3) transport package models.

Table 2-27. Mechanical Connector Impact Load Summary - All Models Model Impact Load (lbs.)

Applied Load (lbs.)

Total Connector Load (lbs.)

Quantity of Effective Connectors Load/

Connector (lbs.)

AOS-025 1.80 x 105 1.861 x 105 306.4 2

153 AOS-050 3.30 x 105 3.738 x 105 598.5 2

300 AOS-100 1.36 x 106 1.500 x 106 2,370.0 2

1,185 Table 2-28. Mechanical Connector Loads for 10g Inertia Force - All Models Model Limiter Weight (lbs.)

Connector Load (P)

(lbs.)

AOS-025 14.0 17.5 AOS-050 62.0 77.5 AOS-100 515.0 643.8

2-66 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.3.2.9.1 Mechanical Connector Stress Analysis - Model AOS-025 In the Model AOS-050 transport package, the critical stress is the connection of the skin and J-bolt box.

For the bearing, use F = 18.0 ksi. (Refer to Figure 2-18.)

Figure 2-18. Critical Stress at Skin and J-Bolt Box Connection - Model AOS-025 where:

A

=

1.0 in.

t

=

0.05 in.

P

=

153 lbs.

=

P / A

  • t = 153 (1.0
  • 0.05) = 3.06 ksi F

=

18.0 ksi MS

=

(18.0 / 3.06) - 1 = 4.9 Skin J-bolt box P

A P

Radioactive Material Transport Packaging System Safety Analysis Report 2-67 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.3.2.9.2 Mechanical Connector Stress Analysis - Model AOS-050 In the Model AOS-050 transport package, the critical stress is the bearing of a connector pin on a rib.

For the bearing, use F = 40.0 ksi. (Refer to Figure 2-19.)

Figure 2-19. Critical Stress at Rib Connector Pins Bearing - Models AOS-050 and AOS-100 where:

d

=

0.125 in.

t

=

0.09 in.

P

=

300 lbs.

A

=

d

  • t

=

P / A = 300 / (0.125

  • 0.09) = 26.7 ksi F

=

40.0 ksi MS

=

(40.0 / 26.7) - 1 = 0.50 d

P

2-68 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.3.2.9.3 Mechanical Connector Stress Analysis - Model AOS-100 In the Model AOS-100 transport package, the critical stress is the bearing of a connector pin on a rib.

For the bearing, use F = 40.0 ksi. (Refer to Figure 2-19.)

where:

d

=

0.5 in.

t

=

0.125 in.

P

=

1,185 lbs.

A

=

d

  • t

=

P / A = 1,185 (0.5

  • 0.125) = 19.0 ksi F

=

40.0 ksi MS

=

(40.0 / 19.0) - 1 = 1.10

Radioactive Material Transport Packaging System Safety Analysis Report 2-69 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.3.3 Analyses of Shielding Devices Note: Analyses of the axial shielding plates (Models AOS-050A, AOS-100A, and AOS-100A-S) and cavity spacer plates (Models AOS-100A and AOS-100A-S) are provided in Appendix 2.12.15.

2.5.3.3.1 Stress Analysis of Cavity Liner - Model AOS-025 The Model AOS-025s tungsten alloy cavity liner is analyzed for stress due to maximum accelerations under 9-m (30-ft.)-drop impact loadings.

Note: The acceleration values used for this analysis envelopes the maximum accelerations.

The following data is used in the analysis:

Longitudinal Acceleration Az =

2,072 g Lateral Acceleration Ay =

1,707 g Elastic Modulus E

=

45.0 x 106 lb/in2 Poissons Ratio

=

0.3 Yield Stress Fy =

94.0 x 103 lb/in2 Density

=

0.7 lb/in3 (actual density is 0.655, rounded up to the more-conservative value, 0.7)

The cavity liner is analyzed using the LIBRA FEA program. The LIBRA model for this analysis is illustrated in Figure 2-20. The model contains 35,966 nodes and 30,400 elements, comprising 107,871 degrees of freedom. A 180° liner segment, with symmetry boundary conditions, is analyzed. The liner is analyzed separately for a 2,072 g longitudinal (Z direction) inertia loading, and a 1,707 g lateral (Y direction) inertia loading. For longitudinal loading, the cross-section at one end of the liner is fixed against longitudinal motion. For transverse loading, a longitudinal line of nodes is fixed against lateral motion. A small hole at the liner ends is included, to facilitate modeling. The LIBRA pre-conditioned conjugate gradient (PCG) solver is used.

The cavity liner equivalent (Von Mises) stress due to the longitudinal inertia loading is illustrated in Figure 2-21. The maximum equivalent stress for longitudinal loading is fe = 8.83 ksi. The minimum margin of safety is then:

MS = Fy / fe - 1 = 94.0 / 8.83 - 1 = 9.6 The cavity liner equivalent stress due to transverse inertia loading is illustrated in Figure 2-22. From Figure 2-22, the liner maximum equivalent stress under transverse inertia load is fe = 16.2 ksi. The minimum margin of safety is then:

MS = Fy / fe - 1 = 94.0 / 16.2 - 1 = 4.8

2-70 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-20. LIBRA Liner Model - Model AOS-025 Symmetry Boundary Longitudinal Boundary Lateral Boundary Lateral Acceleration Longitudinal Acceleration

Radioactive Material Transport Packaging System Safety Analysis Report 2-71 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-21. Equivalent Stress Due to Longitudinal Acceleration - Model AOS-025

2-72 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-22. Equivalent Stress Due to Transverse Acceleration - Model AOS-025

Radioactive Material Transport Packaging System Safety Analysis Report 2-73 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.5.3.3.2 DELETED CONTENT DELETED - Refer to Paragraph 2.12.15.5.

Figure 2-23. DELETED Figure 2-24. DELETED

2-74 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.6 NORMAL CONDITIONS OF TRANSPORT The AOS Transport Packaging System meets the requirements of Normal conditions of transport, as required in 10 CFR 71.71 [2.1] and IAEA Standard [2.2].

Normal conditions of transport are evaluated using the LIBRA Finite Element computer program. The LIBRA program conducts both linear and non-linear, static and dynamic, structural analyses. The LIBRA element library contains more than 60 elements, which include beam, shell, and standard and hierarchical 2D and 3D elements. The program contains 20 solution algorithms. The principal solution algorithms are static analysis, modal analysis, direct and modal dynamic response analysis, and heat transfer. As discussed in Paragraph 2.1.2.4, three (3) Finite Element Analysis (FEA) analytical models are used in the evaluation.

Refer to Subsection 2.6.11 for a tabulation of the minimum Margin of Safety (MS) resulting from Normal conditions of transport.

2.6.1 Heat The thermal evaluation for the heat condition is presented in Chapter 3, Thermal Evaluation. The heat condition consists of exposing the cask to direct sunlight and 38°C (100°F) still air. Insolation of the package is specified in 10 CFR 71.71(c)(1) [2.1]. An initial temperature field of 21°C (70°F) and a maximum internal heat of the respective model are used for the evaluation. In addition, the decay heat of the content must be accounted for in some of the required analyses. The seven (7) thermal conditions (analyses) required to satisfy the regulations are tabulated in Table 2-29.

The thermal loading temperature fields, Load Cases 101 through 106, 111, and 112, are taken directly from the heat transfer analyses, and applied to the stress models. The heat transfer and stress models are geometrically identical, with the same node numbering used in both analyses.

Table 2-29. Transport Package Thermal Environment Conditions - All Models Condition Thermal Environment 1

38°C (100°F) ambient with maximum decay heat and maximum solar load.

2 38°C (100°F) ambient with maximum decay heat.

3 Fire transient, t = 0 to 8.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

4

-40°C (-40°F) ambient with maximum decay heat.

5

-40°C (-40°F) ambient.

6

-29°C (-20°F) ambient with maximum decay heat.

7

-29°C (-20°F) ambient.

Radioactive Material Transport Packaging System Safety Analysis Report 2-75 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.6.1.1 Summary of Pressures and Temperatures Table 2-30 presents the maximum temperatures, throughout the transport package, resulting from Normal conditions of transport. The structural analyses are applied to the temperature field generated by the thermal analysis, to determine the thermal stresses.

Table 2-31 presents the pressure corresponding to the maximum temperature for each transport package model. This pressure value is based upon air at 100% relative humidity occupying the entire cavity volume.

These pressures do not exceed the design pressure, which is also listed in Table 2-31. Therefore, the transport package can withstand pressures and temperatures in excess of those encountered in Normal conditions of transport.

Pressure-related Load Cases 201 through 204 are analyzed by the 2D cask model. Pressure is applied to the models inside cask cavity wall or cask outside surface. The LIBRA LE -4a loading function is used to apply pressure loads. This function generates nodal forces in 2D models due to surface tractions along edge nodal lines. The nodal lines are defined by terminal nodes.

a. The LIBRA programs LE feature defines several types of edge and surface loadings. The first entry is a negative integer that distinguishes the type of loading. The types of loadings and nodal specifications are listed below, with former record types in parentheses.

Options Available when Applying the LE Command Type General loading on nodes specified by numbering sequence.

Type General loading on arc defined by control points (LE1).

Type Surface pressure on arc defined by control points (LEP).

Type Linearly varying pressure on line specified by end nodes.

Type Linearly varying harmonic pressure on 3D model generated from a 2D model.

Further Details for Types -4 and -5 Type This command generates nodal loads corresponding to linearly varying surface tractions along a line on a 2D model. The line is specified by the two (2) terminal nodes, and loads are applied to all nodes within a specified distance of the line. The linearly varying pressure is specified by the terminal values.

Type This command generates nodal loads corresponding to surface tractions over a 3D model generated from an axisymmetric (2D) model. The tractions may vary linearly along a radial line, and circumferentially as a Fourier harmonic. The loaded nodes are identified by specifying the two (2) terminal nodes on the zero meridian. The linearly varying pressure is specified by the corresponding terminal values on the zero meridian.

2-76 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-30. Temperature Summary of Normal Conditions of Transport - All Models Package Component Maximum Temperatures, by Model AOS-025A AOS-050A AOS-100A AOS-100A-S AOS-100B

°C

°F

°C

°F

°C

°F

°C

°F Cask Cavity 125 257 147 296 155 312 156 312 Shielding Material 124 256 142 288 148 298 148 298 Cask Lid Seal Area 124 255 141 286 145 293 145 293 Cask Vent Port 124 255 140 284 143 290 143 290 Cask Drain Port 124 255 141 286 144 291 144 291 Test Port 124 255 141 286 145 293 145 293 Cask Vent Port Pipe Plug 124 255 140 285 143 290 143 290 Cask Drain Port Pipe Plug 124 255 141 286 144 292 144 292 Cask Vent Port Conical Seal 124 255 141 286 145 293 145 293 Cask Drain Port Conical Seal 124 255 142 288 147 296 147 297 Cask Outside Surface 124 256 142 287 146 295 146 295 Impact Limiter, Foam Materials 94 202 117 242 111 231 111 231 Accessible Outside Surface 48 119 45 113 41 106 41 106 Table 2-31. Maximum Cask Cavity Pressure Due to Normal Conditions of Transport - All Models Model Temperature Pressurea

a. Pressure calculation is based upon the ideal gas law illustrated in Table 4-6, Maximum Cask Cavity Pressure Due to Normal Conditions of Transport - All Models, footnote a.

Design Pressureb

b. Model AOS-100 transport package - Pressure value is based upon projected operating conditions.

°C

°F kPa psia kPa psia AOS-025A 125 257 135 20 207 30 AOS-050A 147 296 142 21 414 60 AOS-100A AOS-100A-S 155 312 145 21 1,930 280 AOS-100B 156 312 145 21 1,930 280

Radioactive Material Transport Packaging System Safety Analysis Report 2-77 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.6.1.2 Differential Thermal Expansion The effects of thermal gradients on the AOS Transport Packaging System are included in the LIBRA Finite Element analyses. Therefore, these effects are also included in the Load Combination procedure, where maximum stress and stress margins are calculated. Refer to Table 2-37 and Table 2-56 for Normal and Hypothetical Accident conditions of transport, respectively.

2.6.1.3 Stress Calculations This paragraph describes the effects of the following:

Thermal Stresses (stresses induced within a structure when some or all of the parts are not free to expand nor contract in response to temperature changes)

Design Pressure Stresses (stresses induced by pressure differentials)

Fabrication Stresses (stresses resulting from welding operations) 2.6.1.3.1 Thermal Stresses The thermal loading temperature fields, Load Cases 101 through 106, 111, and 112, are taken directly from the heat transfer analyses, and applied to the stress models. The heat transfer and stress models are geometrically identical, with the same node numbering used in both analyses.

2.6.1.3.2 Design Pressure Stresses Pressure-related Load Cases 201 through 204 are analyzed by the 2D cask model. Pressure is applied to the models inside cask cavity wall, or cask outside surface. The LIBRA LE -4a loading function is used to apply pressure loads. This function generates nodal forces in 2D models due to surface tractions along edge nodal lines, and the nodal lines are defined by terminal nodes.

2.6.1.3.3 Fabrication Stresses Fabrication stress loading is a displacement field modeling cask deformation due to welding. The displacement field produces bending at the weld cross-section, as illustrated in Figure 2-25. A configuration of the weld is also shown for clarification. Dimensions provided in the weld sketch are those for the Model AOS-100. Equal and opposite displacements are applied to the inside surface of the cask cavity shell upper ring, and cask outer shell, and produce a prying load upon the dog-leg section of the inside shell. The dog-leg section is one of the most highly stressed locations within the cask.

The magnitude of the applied displacement is based upon observed welding deformation. For the Model AOS-025, the applied displacement is 0.003175 mm (0.000125 in.). For the Model AOS-050 and AOS-100, the applied displacement is 0.0127 mm (0.0005 in.).

a. Ibid (refer to previous LIBRA LE -4 footnote a).

2-78 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-25. Typical Corner Cask Cavity Shell Weld Joint Configuration - All Models

Radioactive Material Transport Packaging System Safety Analysis Report 2-79 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.6.1.4 Comparison with Allowable Stresses Load Combinations 101 and 106 account for Heat Environment conditions of the Load Cases defined in Table 2-33. (The referenced tables for each model are located in Appendix 2.12.2, Structural Evaluation Results - Models AOS-025, AOS-050, and AOS-100, within their respective paragraphs.)

2.6.2 Cold The transport package must be able to withstand an ambient temperature of -40°C and -29°C (-40°F and

-20°F, respectively), in still air and in the shade. Load Combinations 102, 105, and 107 account for Cold Environment conditions of the Load Cases defined in Table 2-33. (The referenced tables for each model are located in Appendix 2.12.2, Structural Evaluation Results - Models AOS-025, AOS-050, and AOS-100, within their respective paragraphs.) For details regarding the specific conditions related to each of the listed Load Cases and Load Combinations, refer to Table 2-36 and Table 2-37, respectively.

Low-temperature service does not affect the AOS Transport Packaging System, because the majority of structural components are fabricated of SS300, a material that does not undergo ductile-to-brittle transition in the temperature range of interest, down to -40°C (-40°F). For the cask lid attachment bolt material -

nickel alloy ASME SB-637, UNS N07718 - brittle failure is not a consideration per paragraph NB-2311(a)(7), in Reference [2.26], and the General Plastics FR-3700 series foam material has an operating temperature range down to -54°C (-65°F).

Table 2-32. Stresses Resulting from Load Combinations Associated with Heat Environment under Normal Conditions of Transport - All Models Load Combinations Load Cases Description Data, by Model AOS-025A AOS-050A AOS-100A AOS_100A-S AOS-100B 101 102, 201, 211 Hot Environment Table 2-84 Table 2-153 Table 2-222 Table 2-290 106 101, 201, 203, 211 Maximum Pressure, Hot Environment Table 2-89 Table 2-158 Table 2-227 Table 2-295 Table 2-33. Stresses Resulting from Load Combinations Associated with Cold Environment under Normal Conditions of Transport - All Models Load Combinations Load Cases Description Data, by Model AOS-025A AOS-050A AOS-100A AOS_100A-S AOS-100B 102 104, 201, 211 Cold Environment Table 2-85 Table 2-154 Table 2-223 Table 2-291 105 105, 201, 202, 211 Cold Environment with Maximum Decay Heat Table 2-88 Table 2-157 Table 2-226 Table 2-294 107 105, 201, 203, 211 Maximum Pressure, Cold Environment Table 2-90 Table 2-159 Table 2-228 Table 2-296

2-80 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.6.3 Reduced External Pressure Pressure-related Load Cases 201 through 204 are analyzed by the 2D cask model. Pressure is applied to the models inside cask cavity wall or cask outside surface. The LIBRA LE -4a loading function is used to apply pressure loads. This function generates nodal forces in 2D models due to surface tractions along edge nodal lines. The nodal lines are defined by terminal nodes.

Load Cases 201 through 204 include the greatest pressure difference between the inside and outside of the transport package, as well as the inside and outside of the containment system, and are used to evaluate this condition in combination with the maximum normal operating pressure.

2.6.4 Increased External Pressure The analysis for this condition is conducted in a similar manner as in Subsection 2.6.3. Pressure-related Load Cases 201 through 204 are analyzed by the 2D cask model. Pressure is applied to the models inside cask cavity wall or cask outside surface. The LIBRA LE -4 loading function is used to apply pressure loads.

This function generates nodal forces in 2D models due to surface tractions along edge nodal lines. The nodal lines are defined by terminal nodes.

Load Cases 201 through 204 include the greatest pressure difference between the inside and outside of the package, as well as the inside and outside of the containment system, and are used to evaluate this condition in combination with the maximum design operating pressure.

a. Ibid (refer to previous LIBRA LE -4 footnote a).

Radioactive Material Transport Packaging System Safety Analysis Report 2-81 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.6.5 Vibration Vibration and shock loads are analyzed using the 3D model in three (3) separate analyses. The vibration and shock loads are, conservatively, assumed to be:

Load Case 221 - Forward 10g Vibration Inertia Load Load Case 222 - Lateral 5g Vibration Inertia Load Load Case 223 - Vertical 2g Vibration Inertia Load In each analysis, displacements are fixed at the trunnions, and vertical displacement is fixed along the cask and truck bed contact line. The fixed nodes are illustrated in Figure 2-26. The inertia loads are applied as body forces.

The analytical procedure applied to the cask lid attachment bolts of the AOS Transport Packaging System account for fatigue and vibration loads, in addition to preload, pressure, and temperature loads. Procedure setup provides infinite life service (1 x 106 cycles), based upon the ASME Code, Reference [2.14]. (Refer to Appendix 4.5.2, Fortran Program Used to Analyze Cask Lid Attachment Bolts (Reference [4.6]),

for details.)

Figure 2-26. Fixed Points for Shock and Vibration Analyses Fixed Meridian Trunnion

2-82 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.6.6 Water Spray The containment capabilities of the AOS Transport Packaging System are not compromised by water spray, because all external surfaces are comprised of stainless steel, and the closure seal is impervious to water. Furthermore, it is shown that the containment boundary of the AOS Transport Packaging System cask component is leak-tight, thus preventing water from entering the cask cavity. Refer to Chapter 4, Containment, for a description of the containment boundary and its capability to prevent leakage.

2.6.7 Free Drop Each AOS Transport Packaging System model was analyzed to the effect of a free drop, using the LIBRA code. The transport package models were evaluated for a drop distance, based upon the models weight, as listed in Table 2-34. The Drop condition evaluation is based upon the energy displacement curves developed by the 30-ft. drop analysis. The maximum displacements are determined from the energy displacement curves, and are listed in Table 2-35.

The analyses conducted consider three (3) orientations, as illustrated in Figure 2-27. The orientation that produced the most stress upon the cask component of the AOS Transport Packaging System was used as the load condition to be included in the Load Combination procedure.

Table 2-34. Free-Drop Distance - All Models Model Maximum Authorized Package Weighta

a. The weights that comprise the maximum authorized package weight are defined in Table 2-7.

Free-Drop Distance kg lbs.

m ft.

AOS-025A 100 220 1.2 4

AOS-050A 681 1,500 1.2 4

AOS-100A 5,675 12,500 0.9 3

AOS-100B 4,994 11,000 AOS-100A-S 5,675 12,500 Table 2-35. Maximum Displacements in Free Drops, Normal Conditions of Transport - All Models Model Drop Head-On Side Cg/Corner cm in.

cm in.

cm in.

cm in.

AOS-025 121.9 48.0 1.52 0.60 0.96 0.38 2.54 1.00 AOS-050 121.9 48.0 3.81 1.50 3.05 1.20 6.73 2.65 AOS-100 91.4 36.0 6.60 2.60 5.08 2.00 12.19 4.80

Radioactive Material Transport Packaging System Safety Analysis Report 2-83 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-27. Head-On, Side, and Slap-Down Free-Drop Orientations 2.6.8 Corner Drop Not applicable. This requirement applies only to fiberboard, wood, or fissile material rectangular packages not exceeding 50 kg (110 lbs.) and fiberboard, wood, or fissile materials not exceeding 100 kg (220 lbs.).

2.6.9 Compression The compression load of five times (5x) the cask weight is applied to the cask under Load Case 215. This analysis uses the 2D model. The compression force is applied to the top of the cask as a pressure loading, using the LE -4 load function.

2.6.10 Penetration The regulations for Normal conditions of transport stipulate that the transport package must be capable of withstanding the impact of the hemispherical end of a vertical steel cylinder, that:

Weighs 6 kg (13.23 lbs.)

Has a 3.2-cm (1.26-in.) diameter Is dropped from a height of 1 m (40 in.), normally onto the exposed surface of the package that is expected to be the most vulnerable to puncture The impact of a rod falling onto the cask, Load Case 216, was analyzed by a direct integration, dynamic analysis. The cask was modeled by the 2D model illustrated in Figure 2-28. The cask was assumed fixed at the base, and an impulse corresponding to the momentum impacting rod was applied at the top of the cask. Displacement at the impact point was monitored, as illustrated in Figure 2-29. The stress state at the time of maximum displacement was used for stress evaluation.

Head-On Drop Side Drop Slap-Down Drop

2-84 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-28. Rod Impact Analysis Load Distribution - Model AOS-100

Radioactive Material Transport Packaging System Safety Analysis Report 2-85 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-29. Rod Impact Time History Displacement at Impact Node - Model AOS-100

2-86 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.6.11 Structural Evaluation Results Summary and Minimum Margins of Safety under Normal Conditions of Transport In this subsection, the resulting stresses from analyses for Normal conditions of transport are combined, following Reference [2.4] guidelines.

Table 2-36 and Table 2-37 identify the particular table in which the resulting stresses are reported for each AOS Transport Packaging System model, for all Normal conditions of transport Load Cases and Load Combinations, respectively. The referenced tables for each model are located in Appendix 2.12.2, Structural Evaluation Results - Models AOS-025, AOS-050, and AOS-100, within their respective paragraphs.

Paragraph 2.6.11.1 provides the Minimum Margin of Safety (MS) obtained for each Load Combination and System model, under Normal conditions of transport.

This data shows that the AOS Transport Packaging System has the capacity to endure all Normal conditions of transport, without affecting its ability to contain and shield the radioactive material payload from undue risk to the public.

Radioactive Material Transport Packaging System Safety Analysis Report 2-87 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-36. Load Cases under Normal Conditions of Transport Structural Evaluation Results - All Models Load Case Description Data, by Model AOS-025A AOS-050A AOS-100A AOS-100A-S AOS-100B 101 100°F Ambient, Maximum Decay Heat Table 2-66 Table 2-135 Table 2-204 Table 2-272 102 100°F Ambient, Maximum Decay Heat, Maximum Insolation Table 2-67 Table 2-136 Table 2-205 Table 2-273 103

-20°F Ambient, Zero Decay Heat, Zero Insolation Table 2-68 Table 2-137 Table 2-206 Table 2-274 104

-40°F Ambient, Zero Decay Heat, Zero Insolation Table 2-69 Table 2-138 Table 2-207 Table 2-275 105

-40°F Ambient, Maximum Decay Heat Table 2-70 Table 2-139 Table 2-208 Table 2-276 106

-20°F Ambient, Maximum Decay Heat Table 2-71 Table 2-140 Table 2-209 Table 2-277 201 Internal Design Pressure Table 2-72 Table 2-141 Table 2-210 Table 2-278 202 Minimum External Pressure, 24 kPa (3.5 psia)

Table 2-73 Table 2-142 Table 2-211 Table 2-279 203 Maximum Increased External Pressure, 140 kPa (20 psia)

Table 2-74 Table 2-143 Table 2-212 Table 2-280 204 Additional Increased External Pressure, 2 MPa (290 psia)

Table 2-75 Table 2-144 Table 2-213 Table 2-281 211 Fabrication Stress Table 2-76 Table 2-145 Table 2-214 Table 2-282 215 Compression Load (5x weight)

Table 2-77 Table 2-146 Table 2-215 Table 2-283 216 Rod Drop onto Cask Table 2-78 Table 2-147 Table 2-216 Table 2-284 221 Forward 10g Vibration Inertia Load Table 2-79 Table 2-148 Table 2-217 Table 2-285 222 Lateral 5g Vibration Inertia Load Table 2-80 Table 2-149 Table 2-218 Table 2-286 223 Vertical 2g Vibration Inertia Load Table 2-81 Table 2-150 Table 2-219 Table 2-287 231 3-or 4-ft. Head-On Drop Table 2-82 Table 2-151 Table 2-220 Table 2-288 232 30-ft. Head-On Drop Impact Test, Normal Conditions Table 2-83 Table 2-152 Table 2-221 Table 2-289

2-88 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-37. Load Combinations under Normal Conditions of Transport Structural Evaluation Results - All Models Load Combination Load Cases Description Data, by Model AOS-025A AOS-050A AOS-100A AOS-100A-S AOS-100B 101 102, 201, 211 Hot Environment Table 2-84 Table 2-153 Table 2-222 Table 2-290 102 104, 201, 211 Cold Environment Table 2-85 Table 2-154 Table 2-223 Table 2-291 103 103, 202, 211 Increased External Pressure Table 2-86 Table 2-155 Table 2-224 Table 2-292 104 101, 201, 202, 211 Minimum External Pressure Table 2-87 Table 2-156 Table 2-225 Table 2-293 105 105, 201, 202, 211 Cold Environment with Maximum Decay Heat Table 2-88 Table 2-157 Table 2-226 Table 2-294 106 101, 201, 203, 211 Maximum Pressure, Hot Environment Table 2-89 Table 2-158 Table 2-227 Table 2-295 107 105, 201, 203, 211 Maximum Pressure, Cold Environment Table 2-90 Table 2-159 Table 2-228 Table 2-296 215 215, 101, 201, 211 Compression Load Table 2-91 Table 2-160 Table 2-229 Table 2-297 216 216, 101, 201, 211 Rod Drop Table 2-92 Table 2-161 Table 2-230 Table 2-298 217 216, 104, 201, 211 Rod Drop, Cold Environment Table 2-93 Table 2-162 Table 2-231 Table 2-299 221 221, 101, 201, 211 Forward Vibration Table 2-94 Table 2-163 Table 2-232 Table 2-300 222 222, 101, 201, 211 Lateral Vibration Table 2-95 Table 2-164 Table 2-233 Table 2-301 223 223, 101, 201, 211 Vertical Vibration Table 2-96 Table 2-165 Table 2-234 Table 2-302 224 221, 103, 201, 211 Forward Vibration at Cold Temperature Table 2-97 Table 2-166 Table 2-235 Table 2-303 225 222, 103, 201, 211 Lateral Vibration at Cold Temperature Table 2-98 Table 2-167 Table 2-236 Table 2-304 226 223, 103, 201, 211 Vertical Vibration at Cold Temperature Table 2-99 Table 2-168 Table 2-237 Table 2-305

Radioactive Material Transport Packaging System Safety Analysis Report 2-89 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 231 231, 102, 201, 211 3-or 4-ft.

Head-On Drop, Normal Conditions Table 2-100 Table 2-169 Table 2-238 Table 2-306 232a 232, 102, 201, 211 30-ft. Head-On Drop, Normal Conditions (Impact Test)

Table 2-101 Table 2-170 233 231, 103, 211 3-or 4-ft. Drop at Cold Temperature Table 2-102 Table 2-171 Table 2-239 Table 2-307

a. Load Combination 232 is documented only for the Model AOS-025A and AOS-050A transport packages, and demonstrates compliance with the requirements of IAEA TS-R-1, Paragraph 737 (Reference [2.2]).

Table 2-37. Load Combinations under Normal Conditions of Transport Structural Evaluation Results - All Models (Continued)

Load Combination Load Cases Description Data, by Model AOS-025A AOS-050A AOS-100A AOS-100A-S AOS-100B

2-90 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.6.11.1 Minimum Margins of Safety Table 2-38 through Table 2-41 provide the Minimum Margin of Safety (MS) obtained for each Load Combination and Transport Packaging System model, under Normal conditions of transport.

Table 2-38. Min MS for Normal Conditions of Transport - Model AOS-025A Ld_Cmb Load_Cases Min_MS Loc Str_Cmb 101 102 201 211 0 0 5.630E+00 20 Pm+Pb 102 104 201 211 0 0 2.146E+00 5 Pm+Pb+Q 103 103 202 211 0 0 2.841E+00 5 Pm+Pb+Q 104 101 201 202 211 0 2.943E+00 20 Pm+Pb 105 105 201 202 211 0 2.943E+00 20 Pm+Pb 106 101 201 203 211 0 2.889E+00 20 Pm+Pb 107 105 201 203 211 0 2.889E+00 20 Pm+Pb 215 215 101 201 211 0 5.457E+00 20 Pm+Pb 216 216 101 201 211 0 3.306E-01 15 Pm 217 216 104 201 211 0 3.306E-01 15 Pm 221 221 101 201 211 0 5.612E+00 20 Pm+Pb 222 222 101 201 211 0 5.567E+00 20 Pm+Pb 223 223 101 201 211 0 5.505E+00 20 Pm+Pb 224 221 103 201 211 0 2.717E+00 5 Pm+Pb+Q 225 222 103 201 211 0 2.704E+00 5 Pm+Pb+Q 226 223 103 201 211 0 2.686E+00 5 Pm+Pb+Q 231 231 102 201 211 0 2.821E+00 4 Pm+Pb 232 232 102 201 211 0 2.354E+00 4 Pm+Pb 233 231 103 211 0 0 2.678E+00 5 Pm+Pb+Q Table 2-39. Min MS for Normal Conditions of Transport - Model AOS-050A Ld_Cmb Load_Cases Min_MS Loc Str_Cmb 101 102 201 211 0 0 5.819E+00 4 Pm+Pb 102 104 201 211 0 0 2.164E+00 5 Pm+Pb+Q 103 103 202 211 0 0 2.771E+00 5 Pm+Pb+Q 104 101 201 202 211 0 5.535E+00 4 Pm+Pb 105 105 201 202 211 0 5.535E+00 4 Pm+Pb 106 101 201 203 211 0 4.918E+00 4 Pm+Pb 107 105 201 203 211 0 4.918E+00 4 Pm+Pb 215 215 101 201 211 0 4.990E+00 4 Pm+Pb 216 216 101 201 211 0 1.285E+00 15 Pm 217 216 104 201 211 0 1.285E+00 15 Pm 221 221 101 201 211 0 5.732E+00 4 Pm+Pb 222 222 101 201 211 0 5.775E+00 4 Pm+Pb 223 223 101 201 211 0 5.816E+00 4 Pm+Pb 224 221 103 201 211 0 2.681E+00 5 Pm+Pb+Q 225 222 103 201 211 0 2.684E+00 5 Pm+Pb+Q 226 223 103 201 211 0 2.686E+00 5 Pm+Pb+Q 231 231 102 201 211 0 3.266E+00 4 Pm+Pb 232 232 102 201 211 0 1.032E+00 4 Pm+Pb 233 231 103 211 0 0 2.454E+00 5 Pm+Pb+Q

Radioactive Material Transport Packaging System Safety Analysis Report 2-91 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-40. Min MS for Normal Conditions of Transport - Model AOS-100A and AOS-100A-S Ld_Cmb Load_Cases Min_MS Loc Str_Cmb 101 102 201 211 0 0 1.196E+00 4 Pm+Pb 102 104 201 211 0 0 1.196E+00 4 Pm+Pb 103 103 202 211 0 0 5.387E+00 5 Pm+Pb+Q 104 101 201 202 211 0 1.146E+00 4 Pm+Pb 105 105 201 202 211 0 1.146E+00 4 Pm+Pb 106 101 201 203 211 0 1.087E+00 4 Pm+Pb 107 105 201 203 211 0 1.087E+00 4 Pm+Pb 215 215 101 201 211 0 9.375E-01 4 Pm+Pb 216 216 101 201 211 0 1.128E+00 15 Pm+Pb 217 216 104 201 211 0 1.128E+00 15 Pm+Pb 221 221 101 201 211 0 1.068E+00 4 Pm+Pb 222 222 101 201 211 0 1.176E+00 4 Pm+Pb 223 223 101 201 211 0 1.191E+00 4 Pm+Pb 224 221 103 201 211 0 1.068E+00 4 Pm+Pb 225 222 103 201 211 0 1.176E+00 4 Pm+Pb 226 223 103 201 211 0 1.191E+00 4 Pm+Pb 231 231 102 201 211 0 1.127E+00 4 Pm+Pb 233 231 103 211 0 0 5.347E+00 5 Pm+Pb+Q Table 2-41. Min MS for Normal Conditions of Transport - Model AOS-100B Ld_Cmb Load_Cases Min_MS Loc Str_Cmb 101 102 201 211 0 0 1.196E+00 4 Pm+Pb 102 104 201 211 0 0 1.196E+00 4 Pm+Pb 103 103 202 211 0 0 1.101E+01 4 Pm+Pb 104 101 201 202 211 0 1.146E+00 4 Pm+Pb 105 105 201 202 211 0 1.146E+00 4 Pm+Pb 106 101 201 203 211 0 1.087E+00 4 Pm+Pb 107 105 201 203 211 0 1.087E+00 4 Pm+Pb 215 215 101 201 211 0 9.375E-01 4 Pm+Pb 216 216 101 201 211 0 1.128E+00 15 Pm+Pb 217 216 104 201 211 0 1.128E+00 15 Pm+Pb 221 221 101 201 211 0 1.068E+00 4 Pm+Pb 222 222 101 201 211 0 1.176E+00 4 Pm+Pb 223 223 101 201 211 0 1.191E+00 4 Pm+Pb 224 221 103 201 211 0 1.068E+00 4 Pm+Pb 225 222 103 201 211 0 1.176E+00 4 Pm+Pb 226 223 103 201 211 0 1.191E+00 4 Pm+Pb 231 231 102 201 211 0 1.127E+00 4 Pm+Pb 233 231 103 211 0 0 1.043E+01 4 Pm+Pb

2-92 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7 HYPOTHETICAL ACCIDENT CONDITIONS The AOS Transport Packaging System, when subjected to the Hypothetical Accident conditions of transport specified in 10 CFR 71.73, meets the performance requirements specified in 10 CFR 71 [2.1],

Subpart E. This is demonstrated within this section where the Hypothetical Accident conditions of transport are addressed and shown to meet the applicable design criteria provided in Subsection 2.1.2, Design Criteria.

The engineering evaluation for these regulatory conditions was conducted by using the LIBRA Finite Element program. The analytical model used was verified by a Free-Drop test of a 165% scaled-up version of the Model AOS-100A, referred to as AOS-165A and/or prototype in the discussions. The testing conducted and results are also briefly discussed within this section; however, the complete test report is included in Appendix 2.12.6.

The scaled-up Free-Drop test was conducted at General Electric (GE Hitachi Nuclear Energy at the time of this publication), Vallecitos Nuclear Center, Sunol, California, for Alpha-Omega Services, Inc., of Bellflower, California. In addition, Alpha-Omega Services contracted CSA Engineering, Inc., of Mountain View, California, to instrument and record the test results, and RANOR, Inc., of Westminster, Massachusetts, to fabricate the prototype packaging. GE Hitachi Nuclear Energy contracted RANOR, Inc.

to perform pre-and post-dimensional inspections. A copy of the Dimensional Inspection report is included in Appendix 2.12.7.

For Free Drop evaluation, three orientations were analyzed:

Head-On Drop Side Drop, including Slap-Down Cg/Corner Drop The first two drop orientations were correlated to the Free-Drop test data, for validation of the analytical model and procedure used. The correlation work is also included in this section.

Radioactive Material Transport Packaging System Safety Analysis Report 2-93 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1 Free Drop The AOS Transport Packaging System is described in Subsection 2.1.1, Discussion. As discussed in that subsection, the cask component is covered at both ends by the impact limiter. The impact limiter is designed to absorb the energy developed during the drop, mitigating the drops effect on the cask. The analysis presented in this subsection consists of two (2) parts:

To identify the load onto the cask, by conducting a pseudo-static collapse analysis of the impact limiter, and To impose this resulting load onto the cask in the stress analysis Hypothetical Accident conditions of transport are provided in Appendix 2.12.2.

The AOS Transport Packaging System has an axisymmetric geometry. The Head-On Drop is oriented with the cask lid facing down, to produce the maximum damage on the cask lid seal joint. For the Side Drop, the cask is oriented to produce maximum side loading. The Slap-Down Drop is oriented to produce the maximum slap-down loading. The Cg/Corner Drop is oriented such that impact occurs on a line through the cask center of gravity.

Notes:

The Cg/Corner Drop loading condition was not one of the orientations tested. This condition does not produce as critical a load as the Slap-Down loading. Additionally, the design has a recessed cask lid, which protects the cask lid seal and cask lid attachment bolts.

The foam properties used in the free drop analysis are those presented in Appendix 2.12.5 [2.19]

for the foam density values of 20, 10, and 12 pcf. for the Model AOS-025, AOS-050, and AOS-100, respectively.

The Impact (Free-Drop) test is conducted to obtain data to demonstrate the adequacy of analytical methods used for qualifying the transport packages, both at the size tested and scaled-down versions. The AOS-165A was selected for this test because it is the largest package, in terms of size and weight. These analytical methods are used to show that the impact limiters are capable of limiting impact loads on the payload to an acceptable level.

Appendix 2.12.6 presents the Free-Drop Test report, which includes a detailed description of the test procedure. Appendix 2.12.7 presents the Dimensional Inspection report of the impact limiter and cask components, taken throughout the Free-Drop test. Appendix 2.12.13 presents the Certificate of Conformance for the General Plastics LAST-A-FOAM FR-3720 foam used in the AOS-165A prototype.

A 9-m (30-ft.) Drop test is conducted on a 165% scaled-up version of the Model AOS-100A, the AOS-165A prototype. The test article weighs approximately 18,144 kg (40,000 lbs.). Three (3) free drops, each with the package at a different orientation, are conducted as part of the test:

End (Head-On orientation) - Package axis is vertically oriented Side (Side orientation) - Package axis is horizontally oriented Slap-Down - Package axis is oriented at a pre-determined angle with the impact plane to cause maximum slap-down load

2-94 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-30 illustrates the three (3) free drop orientations and test setup. The test sequence listed above can be changed during the tests. High-speed cameras from two (2) orthogonal directions were used to document the orientation prior to each drop. (Refer to Figure 2-31 for camera positioning.)

Acceleration time history data is recorded during the test, using accelerometers located inside the cask and on the impact limiter. A total of 10 sensors are used. One triaxial accelerometer is mounted on the impact limiter, at a location determined by CSA Engineering, Inc. (the company contracted to conduct the test). Two (2) triaxial accelerometers are mounted inside the payload cavity, one on each end of the dummy mass. Each triaxial accelerometer senses in the radial, tangential, and axial directions. The tenth sensor is a uniaxial accelerometer sensing in the vertical direction for the drop.

The impact force distribution on the cask surface is estimated using a pressure-sensing film applied prior to each drop and removed immediately afterward. The film is used on the top and curved surfaces of the cask, enclosed by the impact limiters.

In addition, a series of dimensional inspections of the cask and impact limiter are conducted before and after each drop, to establish the drops resulting deformation pattern.

Figure 2-30. Head-On, Side, and Slap-Down Free-Drop Orientations Head-On Drop Side Drop Slap-Down Drop

Radioactive Material Transport Packaging System Safety Analysis Report 2-95 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

A portable 90-ton hydraulic crane is used to position the package at the proper height of 9m (30 ft.) or greater, above the impact surface. To prevent crane boom backlash after the load is released, the crane hook must be connected to two (2) dead weights by wire rope slings. This maintains the load on the crane after the package is released. (Refer to Figure 2-31.)

A quick-release (air-actuated, pneumatic) mechanism is used to release the package and allow it to fall freely. The mechanism is attached to the crane hook and package holding gear [3.7-m (12-ft.) wire rope sling]. The only connections to the package during the drop are the light instrumentation cables.

The cables are arranged so that they do not interfere with the free-fall path of the package. Attached to the slings is a 3-gallon air accumulator tank and fast-acting, electrically triggered diaphragm valve mounted close to the quick-release mechanism.

Drop height is determined by means of a light, graduated chain or measuring tape, hanging from the lowest point of the package to the ground. After the drop height is verified, the graduated chain or measuring tape is removed prior to the drop.

The primary pass-fail criterion for the test is based upon a Leak Rate test, conducted upon the transport packages cask component before and after the Drop tests. Subsection 8.1.4, Leakage Tests, details the Leak test methodology. An acceptable leak rate is less than 2.96 x 10-7 cm3/sec (helium), at a differential pressure of 1 atmosphere.

Note: For the transport package to be judged acceptable, the measured leak rate must be less than this amount, both before and after the Drop tests.

The secondary criterion relates to external transport package dimensions. These must not have changed by any amount that would prevent or endanger the transport packages performance of its primary functions - containment and shielding.

2-96 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-31. Test Setup (Head-On Orientation Shown) - AOS-165A Prototype Quick Release Mechanism High-Speed Camera Linear and Rotating Scales High-Speed Camera

Radioactive Material Transport Packaging System Safety Analysis Report 2-97 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1.1 End Drop 2.7.1.1.1 Head-On Free-Drop Impact Limiter Analysis - Model AOS-100 The Model AOS-100 transport packages impact limiter structure is composed of General Plastics LAST-A-FOAM FR-3712 foam and 12-gauge (2.7 mm / 0.105 in.) stainless steel cladding. The entire assembly consists of two (2) impact limiters connected by eight (8) turnbuckles. Each impact limiter is approximately 116 cm (45.65 in.) in diameter by 62.5 cm (24.6 in.) in height. There is an uncovered cask length of approximately 56 cm (22 in.) between the impact limiters. The impact limiter end is a spherical, dish shell. In addition, the ends contain a recessed, cylindrical section of approximately 41 cm (16.2 in.) in diameter by 12.4 cm (5.0 in.) in depth.

The foam material accounts for most of the impact limiters energy absorbing capability. The energy absorbed by the cladding is small and not included in this analysis. Also, not included in the analytical models are the eight (8) structural ribs that are part of the impact limiter structure because they have little effect on the behavior of the impact limiter due to the free drop load. The omission of the ribs are justified by the analysis presented in Appendix 2.12.10. The impact limiter foam is analyzed by static, 3D, large displacement, finite element analyses. The foam is modeled by solid elements with Piola-Kirchhoff stress tensors, and FR-3712 foam constitutive behavior. Strain energy developed in the foam is determined for a sequence of applied displacement fields corresponding to the impact of the cask on a rigid plane.

Displacements are applied in 0.25 mm (0.01 in.) increments for both head-on and side drop configurations, until the strain energy developed in the foam equals the potential energy of a 9-m (30-ft.) drop. The configuration corresponding to the maximum slap-down impact is determined from a series of dynamic analyses with different cask impact orientations and side-drop impact properties. The orientation producing maximum impact force is selected as the slap-down configuration.

Figure 2-32 shows the FEA model used in the drop analyses. The model represents a 180° section of the impact limiter and contains 2,835 nodes, 2,220 elements, and 8,496 degrees of freedom. A small, artificial hole is modeled at the axis of rotation of the impact limiter, to restrict the model to 8-node solid elements.

Radial degrees of freedom are fixed at the hole. Foam element constitutive properties are taken from Table 2-14 and Table 2-15.

The interaction between the content and cask lid due to the free drop load is provided in Appendix 2.12.8.

In the impact analysis, a series of displacement fields simulating the head-on impact of the impact limiter onto a rigid surface was applied. The displacement steps correspond to 0.25 mm (0.01 in.) displacements of the rigid surface. The geometric and constitutive element properties were updated after each displacement step. Figure 2-33 illustrates the strain energy developed in the foam, and total force at the rigid surface, as a function of surface displacement. For a 180° model, and 9,510-lb. weight (Model AOS-100 is used for reference), the maximum displacement corresponds to the strain energy.

U = 9,510

  • 360 = 3.42 x 106 in.-lb.

From Figure 2-33, the corresponding displacement is 15.5 cm (6.1 in.), the total force is 1.42 x 106 lbs.,

and the maximum acceleration is:

a = 1.42 x 106 / 9,510 = 149.3g Figure 2-34 shows longitudinal foam displacements, where the displacement contours are plotted on the deformed geometry. The equivalent stress at maximum displacement is plotted in Figure 2-35.

2-98 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-32. Finite Element Model of Impact Limiter - Model AOS-100 Figure 2-33. Head-On Drop Force and Energy - Model AOS-100



U=3.42e6/2=1.71e6 P=2x7.10e5=1.42e6

Radioactive Material Transport Packaging System Safety Analysis Report 2-99 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-34. Head-On Drop, Maximum Foam Displacement (Deformed Model) - Model AOS-100 Figure 2-35. Head-On Drop, Maximum Equivalent Stress in Foam - Model AOS-100

2-100 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1.1.2 Head-On Free-Drop Cask Analysis A net force due to a 30-ft. head-on drop, Load Case 301, is determined from the impact limiter analysis presented in Paragraph 2.7.1.1.1. Stress due to head-on drop loads was analyzed by the 2D cask model.

Figure 2-36 shows the assumed impact load distribution. With reference to Figure 2-36, for a total impact force P, the load intensity is given by:

Over section L, the load intensity in the x and y directions is:

qx = qy = q

  • sin (45°)

The LIBRA LE -4a loading function is used to apply pressure load q. In addition to the impact load, an opposing inertia body force is applied to the cask. Displacements are fixed along the cask base to account for the small non-equilibrium of pressure and inertia forces.

Figure 2-36. Head-On Drop Analysis Load Distribution - All Models

a. Ibid (refer to previous LIBRA LE -4 footnote a).

q = P / (R1 2 - R2

2)

R R

L q

2 1

FIXED DISPLACEMENT

Radioactive Material Transport Packaging System Safety Analysis Report 2-101 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1.1.3 Correlation of Head-On Drop Analysis and Test In the Drop test, a 165% scaled-up version of the Model AOS-100A (referred to as AOS-165A and/or prototype in the discussions) was used. A single cask component of the prototype with multiple impact limiters was subjected to three (3), 9.14-m (30-ft.) Drop tests:

Head-On Drop Side Drop Slap-Down Drop In the Slap-Down Drop test, the cask was oriented with one end offset 25.4 cm (10 in.) above the other.

Following all three (3) tests, the cask showed no measurable deformation, and passed all Leak tests. The only notable structural problem encountered in the Drop tests was the failure of a turnbuckle pin in the Side Drop test. A larger-diameter pin was successfully used in the subsequent Slap-Down Drop test.

Four (4) types of data were gathered before, during, and after each drop test:

Acceleration data from three (3) accelerometers Laser dimensional readings High-speed photographs at 1-ms intervals during impact Photographs of the sectioned, deformed impact limiters The Dimensional Inspection report, presented in Appendix 2.12.7, for the Head-On Drop test, does not provide a direct correlation with the LIBRA analysis, because the laser readings are of the cladding, and the cladding at the center of the impact limiter significantly separated from the foam. A correlation of analysis and test displacement results is obtained from the photo of the sectioned impact limiter, shown in Figure 2-37. This photo provides a measurement of the compressed impact limiter height that can be directly compared to analysis. In Figure 2-37, Dimension A is used to scale the photo measures to design dimensions, and Dimension B is the overall height.

Design Dimensions A

=

46.6 in.

B

=

39.0 in.

Photo Dimensions a

=

4.85 in.

b

=

3.60 in.

Scale Factor X

=

A / a = 46.6 in. / 4.85 in. = 9.61 in.

Compressed Height from Photo B'

=

X

  • b = 9.61 in.
  • 3.60 in. = 34.6 in.

Deflection, B - B'

=

39.0 in. - 34.6 in. = 4.4 in.

The deflection,, corresponds to a displacement of 5.5 in. for a cask weight of 37,500 lbs., in Figure 2-44.

The analysis and measured values differ by 25%.

2-102 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

In addition to correlating maximum displacements, a qualitative comparison of overall displacements is provided by Figure 2-38 and Figure 2-39. Figure 2-38 is a photo of the deformed impact limiter.

Figure 2-39 is a LIBRA-rendered plot of the deformed model. A comparison of these figures shows that the LIBRA deformed model qualitatively compares well with the deformed structure.

The test accelerometer data is dominated by ringing due to vibration of tungsten alloy cylinders, rendering it unsuitable for correlation with the analytical results. A comparison of analytical and test results for head-on, rigid body cask deceleration is obtained using the time to achieve maximum displacement shown on the high-speed photographs, some of which are shown in Figure 2-40. In the Drop Test report, presented in Appendix 2.12.6, the time to achieve maximum displacement is given as 0.021 sec. This time can be calculated by considering the cask and impact limiter to be a single degree of freedom spring-mass system, where the spring is approximated from Figure 2-33, and the mass is the total cask plus impact limiter mass. The period for cask impact limiter, undamped spring-mass system is:

Due to the foam, the cask experienced high damping during impact. The amount of damping is given by the height of the cask rebound. From the Drop Test report (Appendix 2.12.6), the rebound height was approximately 0.9m (3 ft.), 10% of the drop height, indicating that 90% of the kinetic energy was damped.

A series of LIBRA-AGS analyses were conducted, to determine the critical damping coefficient corresponding to a 90% energy loss. As illustrated in Figure 2-42, a critical damping coefficient of

= 0.60 corresponds approximately to a 90% energy loss. The damped period is then:

The impact duration is half the period, T'/2 = 0.041 sec, and corresponds to the time at which the cask separates form the ground. From Figure 2-40, separation time is seen to be approximately 0.042 sec, which corresponds well to T'/2. In addition, the maximum displacement occurs at T'/4 (0.023 sec.), which correlates well with the time observed in the test, 0.021 sec.

k = 5.6 x 10 6 / 6.2 = 0.90 x 10 6 lb/in m = 37,500 / 386.4 = 96.3 lb-sec/in 2

f = (k / m) 0.5 = 96.7 rad/sec = 15.4 Hz T = 1 / f = 0.065 sec T' = T / (1 -

2) 0.5 = 0.065 / 0.80 = 0.0813 sec

Radioactive Material Transport Packaging System Safety Analysis Report 2-103 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-37. Sectioned Impact Limiter Used in Head-On Drop - AOS-165A Prototype A

B

2-104 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-38. Impact Limiter after Head-On Drop - AOS-165A Prototype

Radioactive Material Transport Packaging System Safety Analysis Report 2-105 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-39. Rendered LIBRA Deformed Head-On Drop - AOS-165A Prototype

2-106 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-40. Photograph Frames from High-Speed Video of Head-On Drop - AOS-165A Prototype

Radioactive Material Transport Packaging System Safety Analysis Report 2-107 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-41. Impact Response for Damping,

= 0.06 - AOS-165A Prototype ti damping analysis sc 300000,1.0E-6, 0,0.0114, 0,0,0 nd 1,90.0

, 2,1 = k/m = 105.4 el 1,1,1,2 = 0.06 pr 1,1.0E6 = 2 * / = 0.0114 bc 2 iv 1,527 mo 1,1 end k

c

2-108 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-42. Head-On Drop Force and Energy - AOS-165A Prototype

Radioactive Material Transport Packaging System Safety Analysis Report 2-109 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1.2 Side Drop 2.7.1.2.1 Side Drop Impact Limiter Analysis The FEA model shown in Figure 2-32 is also used for the Side Drop configuration. As in the head-on drop analysis, a series of displacement fields, simulating the side impact of the impact limiter onto a rigid surface, is applied, with displacement steps corresponding to 0.25 mm (0.01 in.) displacements of the rigid surface, and geometric and constitutive element properties updated after each displacement step.

Figure 2-43 illustrates the strain energy and total force developed in the foam due to the rigid surface displacements. For the 180° section of one impact limiter and an 9,510-lb. cask weight, the maximum displacement corresponds to the strain energy:

U = 9,510

  • 360 = 3.42 x 106 in.-lb.

From Figure 2-43, the corresponding displacement is 14.5 cm (5.7 in.), the total force is 1.36 x 106 lbs.,

and the maximum acceleration is:

a = 1.36 x 106 / 9,510 = 143.0g Figure 2-44 illustrates the lateral foam displacements, where the displacement contours are plotted on the deformed geometry. The equivalent stress and strain at maximum displacement are plotted in Figure 2-45 and Figure 2-46, respectively.

Figure 2-43. Side Drop Force and Energy - Model AOS-100 U=3.42e6/4=8.55e5 P=4x3.40e5=1.36e6

2-110 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-44. Side Drop, Maximum Foam Displacement (Deformed Model) - Model AOS-100 Figure 2-45. Side Drop, Maximum Equivalent Stress in Foam - Model AOS-100

Radioactive Material Transport Packaging System Safety Analysis Report 2-111 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-46. Side Drop, Maximum Principal Strain in Foam - Model AOS-100

2-112 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1.2.2 Side Drop Cask Analysis Net force due to a 30-ft. side drop plus slap-down, Load Case 302, is determined from the impact limiter analysis presented in Paragraph 2.7.1.2.1. Figure 2-47 illustrates the assumed impact load distribution.

For impact force P, the load intensity distribution, as a function of the circumferential angle, is assumed to be:

The LIBRA loading function, LE -5a, applies impact traction q. This function applies surface tractions in 3D models generated from 2D models. Tractions are applied along nodal lines of the 2D model. The tractions can vary linearly along the 2D nodal lines, and as a sine or cosine harmonic in the circumferential direction. The above tractions, qx and qz, are applied with LE -5, using the trigonometric identities:

In addition to the impact load, an opposing inertia body force is applied to the cask. Radial displacements are fixed along the cask meridian 180° from center of loading, to account for non-equilibrium of pressure and inertia forces.

a. Ibid (refer to previous LIBRA LE -5 footnote a).

qx = -q

  • cos 2

qz = q

  • sin
  • cos

/2 P = 2L -q

  • cos 2
  • r
  • d

-/2 P =

  • R
  • L
  • q q = P / (
  • R
  • L) qx
  • cos 2 = 1/2
  • qx * (1 + cos 2) qz
  • sin
  • cos = 1/2
  • qz
  • sin 2

Radioactive Material Transport Packaging System Safety Analysis Report 2-113 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-47. Side Drop Analysis Load Distribution - All Models R

q L

q L

2-114 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1.2.3 Correlation of Side-Drop Analysis and Test In the side drop, there is not a significant separation of foam and cladding. (Refer to Figure 2-44.) As a result, the dimensional inspection results are used to correlate test and analysis results. In the analysis, a uniform radial displacement is applied along the impact limiter structure. In the side-drop test, the impact limiter experienced small rotation, producing differences in radial displacement along the impact limiter.

Consequently, the net average test radial displacement in each impact limiter is compared to the uniform analysis displacement. For the AOS-165A prototype, the net average test radial displacements at the two (2) impact limiters are provided in Table 2-42 from the Dimensional Inspection report, presented in Appendix 2.12.7.

The average of displacements is determined at three (3) locations along the impact limiter:

Point 1 - At the impact limiter base Point 2 - Approximately halfway between the impact limiter base and crown Point 3 - At the impact limiter crown The net displacement - the sum of all displacements, at the inside and outside of the impact limiter - is used at each point.

The average radial displacement at Impact Limiter 1 is 8.91794 cm (3.511 in.). The average radial displacement at Impact Limiter 2 is 7.56666 cm (2.979 in.). From Figure 2-43, the average analytical radial displacement is 10.5156 cm (4.14 in.). This analytical value includes a 1.15 slap-down factor.

Table 2-42. Side-Drop Analysis and Test, Radial Displacement at Impact Limiters 1 and 2 - AOS-165A Prototype Impact Limiter 1 (in.)

Impact Limiter 2 (in.)

Area Base Mid Crown Area Base Mid Crown Outside 3.969 2.239 2.080 Outside 4.027 2.057 1.892 Inside 0.547 1.247 0.451 Inside 0.000 0.650 0.311 Total 4.516 3.486 2.531 Total 4.027 2.707 2.203

Radioactive Material Transport Packaging System Safety Analysis Report 2-115 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1.2.4 Side Drop Slap-Down Analysis The Slap-Down drop analysis is used to determine the cask orientation that produces maximum side impact. The impact force is determined by a series of direct integration, dynamic analyses involving different offset values, and the FEA model used for these analyses is shown in Figure 2-48. This model consists of a uniform block, and two (2) linear springs connected to the block by gap elements. Block geometry, total mass, and moment of inertia approximate the cask values. The spring stiffness values approximate stiffness of the impact limiter when subjected to a side drop. In each analysis, a null gap is modeled at one spring, and a gap equal to the offset is modeled at the other spring. The approximate, linear stiffness used for the impact limiter is 0.85 x 106.

Figure 2-49 and Figure 2-50 graphically present the direct integration, dynamic analyses results for the AOS-165A prototype:

Figure 2-49 presents the spring displacement, plotted as a function of support offset.

Figure 2-50 presents the displacements at both springs, plotted as functions of time for an offset of approximately 25.4 cm (10 in.), the offset used in the drop test.

Maximum values from Figure 2-50 are presented in Table 2-43.

Table 2-43. Support Displacements - AOS-165A Prototype Support Maximum Displacement cm in.

1 8.89 3.500 2

10.82 4.260

2-116 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-48. Slap Finite Element Model - AOS-165A Prototype K=8.50E5 lb./in.

Zero Gap K=8.50E5 lb./in.

Offset Gap W = 35k V0 = 527 in/s

Radioactive Material Transport Packaging System Safety Analysis Report 2-117 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-49. Maximum Support Displacement versus Offset - AOS-165A Prototype Figure 2-50. Slap-Down Analysis Support Displacements versus Time - AOS-165A Prototype G = 3.5 G = 4.26 in.

in.

2-118 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1.2.5 Correlation of Slap-Down Drop Analysis and Test The dimensional analysis results are used to correlate Slap-Down test and analysis results. In the analysis, a single radial displacement is assumed for each impact limiter structure. In the Side-Drop test, the impact limiter experienced small rotation, producing differences in radial displacement along the impact limiter.

Consequently, the net average test radial displacement in each impact limiter is compared to the single analysis displacement. For the AOS-165A prototype, the net average test radial displacements at the two (2) impact limiters are provided in Table 2-44, from the Dimensional Inspection report, presented in Appendix 2.12.7.

The average of displacements is determined at three (3) locations along the impact limiter:

Point 1 - At the impact limiter base Point 2 - Approximately halfway between the impact limiter base and crown Point 3 - At the impact limiter crown The net displacement - the sum of all displacements, at the inside and outside of the impact limiter - is used at each point.

The average radial displacement at Impact Limiter 1 is 7.14756 cm (2.814 in.). The average radial displacement at Impact Limiter 2 is 9.53516 cm (3.754 in.). From Figure 2-50, the corresponding analytical radial displacements are 8.89 cm (3.50 in.) and 10.8204 cm (4.26 in.). The analysis and test results differ by a maximum of 19.6%. The test and analysis ratio of displacements at the impact limiters are 3.302 cm (1.30 in.) for the test and 3.0734 cm (1.21 in.) for the analysis.

Table 2-44. Slap-Down Drop Analysis and Test, Radial Displacement at Impact Limiters 1 and 2 - AOS-165A Prototype Impact Limiter 1 (in.)

Impact Limiter 2 (in.)

Area Base Mid Crown Area Base Mid Crown Outside 3.093 2.090 2.494 Outside 4.080 2.406 2.494 Inside 0.490 0.490 0.274 Inside 0.000 1.581 0.702 Total 3.583 2.580 2.768 Total 4.080 3.987 3.196

Radioactive Material Transport Packaging System Safety Analysis Report 2-119 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1.2.6 Slap-Down Drop Cask Analysis Figure 2-51 illustrates this force distributed over the entire cask surface. For impact forces Px and Py, the load intensity distribution, as a function of the circumferential angle, is assumed to be:

In addition to the impact load, an opposing inertia body force is applied to the cask. Radial displacements are fixed along the cask meridian 180° from center of loading, to account for non-equilibrium of impact and inertia forces.

Figure 2-51. Cg/Corner Drop Analysis Load Distribution - All Models qy = 2/

  • Py / (R2 2 - R3
2) qx = -q
  • cos 2

qz = q

  • sin
  • cos

/2 Px = 2L -q

  • cos 2
  • r
  • d

-/2 qx = 2

  • P / (
  • R1
  • L)

R R

R q

L qx v

3 2

1

2-120 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1.3 Corner Drop As with Head-On and Side Drops, evaluation of the Corner orientation (Cg/Corner) 30-Ft. Drop involves two separate analyses - a foam analysis to determine maximum impact force, and a cask analysis to evaluate cask stress due to impact loading. The impact limiter FEA model illustrated in Figure 2-32 is used to determine the maximum impact loading for a Cg/Corner Drop configuration. As in both the Head-On and Side Drop analyses, a series of 0.25-mm (0.01-in.) displacements of a rigid plane simulating foam impact onto a rigid surface is applied to the model in Figure 2-32. The model geometry and element constitutive properties are updated after each displacement step. The impact force and strain energy developed in the foam are determined in the analysis, and are plotted as functions of the rigid plane displacement. The maximum impact force is determined from the plots, and corresponds to the strain energy equal to the drop potential energy of 9,510 lbs

  • 30 ft., or 3.42 x 106 in-lb. This maximum force is then applied to the FEA model illustrated in Figure 2-7, with the load distribution illustrated in Figure 2-51.

2.7.1.4 Oblique Drops The preceding analytical evaluations, together with the results of the full-scale Drop test presented in Appendix 2.12.6 and Appendix 2.12.7, demonstrate that the AOS Transport Packaging System models can survive the effects of the 9-m (30-ft.) free drop, without breaching containment nor suffering significant deformation on their cask components. In the Free-Drop test (Appendix 2.12.6), the prototype cask was dropped three (3) times, in different orientations, without any significant deformation nor failure of the containment system.

Radioactive Material Transport Packaging System Safety Analysis Report 2-121 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1.5 Summary of Results All analyses associated with the 9-m (30-ft.) cask drops conducted for Models AOS-025, AOS-050, and AOS-100 are summarized within this paragraph.

2.7.1.5.1 9-m (30-ft.) Drop Analyses Table 2-45 lists the six (6) analyses conducted on each of the three (3) cask models, for a total of 18 drop analyses.

Each drop analysis involves two (2) separate analyses. In the first analysis, the impact limiter is analyzed to determine impact loading upon the cask structure. The force-displacement curves generated in the impact limiter drop analyses are presented in Figure 2-54 through Figure 2-63. In the second analysis, the impact loading is applied in a cask stress analysis. Two (2) model types are used in cask stress analyses. Head-On drops are assumed to be axisymmetric, and the 2D cask model illustrated in Figure 2-52 is used. The 3D cask model illustrated in Figure 2-53 is used for Side and Cg/Corner Drop cask stress analyses.

Table 2-45. 9-m (30-ft.) Drop Analyses Conducted upon Each Cask Model Load Case Description 301 30-ft. Head-On Drop at 75°F 302 30-ft. Side Drop + Slap-Down at 75°F 303 30-ft. Cg/Corner Drop at 75°F 304 30-ft. Head-On Drop at -40°F, Low Temperature 305 30-ft. Side Drop + Slap-Down at -40°F, Low Temperature 306 30-ft. Cg/Corner Drop at -40°F, Low Temperature

2-122 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-52. Head-On Drop Cask Model Impact Load Reaction Forces Reaction Forces

Radioactive Material Transport Packaging System Safety Analysis Report 2-123 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-53. Side+Slap-Down and Cg/Corner Drop Cask Model Reaction Forces Side Impact Load CG/Corner Impact Load Side Impact Load Cg/Corner Impact Load Side Impact Load Side Impact Load Reaction Forces

2-124 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-54. Force-Displacement for Head-On Drop at 75°F - Model AOS-025 Note: The foam manufacturer, General Plastics, recommends a 50% strain limit to FR-3700 series foam that has 20-pcf density (FR-3720). This limit applies to nominal strain, and not to strain at every point. The recessed region at the top of the impact limiter has high localized strains under a head-on impact. The FEA model used in the drop analyses requires foam data for strains over 50% to accurately model these local regions. Nominal foam strain in the Model AOS-025 cask for a head-on impact is approximately 35%,

as shown below. The dimensions provided are in inches.

V =

220

  • 360 = 7.92 x 104 in-lb A =

(3.502 - 0.42) = 38.0 in2 f

=

2.168 ksi (40% strain)

P =

A

  • f = 38.0
  • 2.168 = 82.3 k

=

V / P = 79.2 x 103 / 82.3 x 103 = 0.96 in.

=

/ L = 0.96 / 2.75 = 0.35 in/in D = 0.8 L = 2.75 D0 = 7.00

Radioactive Material Transport Packaging System Safety Analysis Report 2-125 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-55. Force-Displacement for Side Drop at 75°F - Model AOS-025

2-126 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-56. Force-Displacement for Cg/Corner Drop at 75°F - Model AOS-025

Radioactive Material Transport Packaging System Safety Analysis Report 2-127 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-57. Force-Displacement for Head-On Drop at 75°F - Model AOS-050

2-128 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-58. Force-Displacement for Side Drop at 75°F - Model AOS-050

Radioactive Material Transport Packaging System Safety Analysis Report 2-129 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-59. Force-Displacement for Cg/Corner Drop at 75°F - Model AOS-050

2-130 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-60. Force-Displacement for Head-On Drop at 75°F - Model AOS-100





U=3.42e6/2=1.71e6 P=2x7.10e5=1.42e6

Radioactive Material Transport Packaging System Safety Analysis Report 2-131 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-61. Force-Displacement for Head-On Drop at -40°F - Model AOS-100 U=3.42e6/2=1.71e6 P=2x8.60e5=1.72e6

2-132 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-62. Force-Displacement for Side Drop at 75°F - Model AOS-100 U=3.42e6/4=8.55e5 P=4x3.40e5=1.36e6

Radioactive Material Transport Packaging System Safety Analysis Report 2-133 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-63. Force-Displacement for Cg/Corner Drop at 75°F - Model AOS-100



U=3.42e6/2=1.71e6 P=2x5.10e5=1.02e6

2-134 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1.5.2 Cask Impact Loadings Figure 2-64 and Figure 2-65 illustrate the impact load distributions applied in the cask stress analyses.

Figure 2-64. Impact Load Distributions Figure 2-65. Circumferential Impact Load Distribution for Side and Cg/Corner Drops 0.571 R 0.286 R Head-On Load Side Load X

Y L/3 Head-On and Cg/Corner Loads

q

  • cos qx = q
  • cos2 qz = q
  • cos
  • sin q
  • cos X

Z

Radioactive Material Transport Packaging System Safety Analysis Report 2-135 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

These distributions are applied over the impact areas observed in the drop tests. The head-on impact load distribution is axisymmetric, and the applied traction, q, is provided by the force, P, divided by the surface area, A:

q = P/A In the LIBRA program, q is entered with an LE -4a command.

The Side and Cg/Corner loadings vary circumferentially, as a cosine function. With reference to Figure 2-64 and Figure 2-65, Side and Cg/Corner surface tractions are provided by the following development:

where:

P

=

Impact load q

=

Prescribed surface traction r

=

Cask outside radius L

=

Cask length

a. Ibid (refer to previous LIBRA LE -4 footnote a).

/2 P = 2 qx

  • r
  • d 0

qx = q

  • cos 2

/2 P = 2q cos 2

  • r
  • d = L
  • r
  • q / 2 0

q = 2P / L

  • r

2-136 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

The traction, q, is applied by its x and z components:

Impact loading is applied with LIBRA LE -4 and LE -5a commands. To apply qx and qz with LE -5, it is necessary to express cos2 and cos

  • sin as functions of 2. Using the trigonometric identities:

The traction x and Z components become:

These surface traction components are entered into LIBRA with LE -4 and LE -5 commands. The constant part of qx is entered with an LE -4 command, and the parts of qx and qz that vary as a function of 2 are entered with an LE -5 command.

2.7.1.5.2.1 Impact Load Tables Impact loads applied in cask stress analyses are summarized in two (2) tables for each AOS model. The first table presents impact loads found in the impact limiter drop analyses, and the corresponding loads upon the cask stress models. The second table presents actual loads applied in the cask stress analyses.

In addition to the impact load, P', an inertial acceleration, A', is applied in the cask stress analyses. The inertia forces prevent large, pseudo-stress at supports, and have only a marginal effect upon maximum stress values. The accelerations are listed in the second table, and are based upon the actual applied impact load and weight of the stress model. The reaction force found in the stress analysis is:

R = P' - (A'

  • M)

This reaction force, R, is listed in the second table. In all cases R/P' is less than 0.01, indicating that the inertia and impact loads differ by less than 1%. Locations of reaction forces are illustrated in Figure 2-52 and Figure 2-53, for head-on and side drops, respectively.

a. Ibid (refer to previous LIBRA LE -4 and LE -5 footnote a).

qx = q

  • cos 2

qz = q

  • cos
  • sin cos 2 = (1 + cos2) / 2 cos
  • sin = (sin2) / 2 qx = q (1 + cos2) / 2 qz = q (sin2) / 2

Radioactive Material Transport Packaging System Safety Analysis Report 2-137 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

In the first table for each of the three (3) cask models, impact loads determined in impact limiter impact analyses are modified by four (4) factors:

Temperature load (fT)

Slap-down load (fS)

Geometric load factor (fG)

Shipping cage impact factor (fP)

Each factor is described in the paragraphs that follow. The impact load applied in the cask analysis is then the product of these four (4) factors and the impact load determined in the impact limiter analysis.

Foam force-displacement properties are approximately 40% higher at -40°F than at 75°F. Results of Head-On Drop analyses for the Model AOS-100 with foam properties at 75°F and -40°F are illustrated in Figure 2-60 and Figure 2-61, respectively. A comparison of these two figures shows that the impact load at

-40°F is approximately 28% higher than the load at 75°F. Although this increase in impact force is less than the increase in force-displacement properties, in the -40°F load cases, a foam temperature load factor of 1.4 is applied to the impact loads at 75°F.

Results of a slap-down study conducted for the AOS-165A prototype illustrated in Figure 2-66 shows that the slap-down load factor is approximately 1.2 (3.035/2.544). Because cask geometries are scaled, this factor is applicable to all AOS models. In Side Drops, Load Cases 302 and 305, impact loads are modified by this slap-down load factor.

A geometric load factor is used to account for model geometry. The Head-On drop uses a 2D model that reflects the full cask, whereas Side and Cg/Corner Drops use only a half model. As a result, impact loads for the full cask are reduced by a 0.5 factor in the Side and Cg/Corner Drop analyses.

Shipping cages add to the cask impact forces, for both Head-On and Cg/Corner 30-ft. Drops. Side Drops, however, are not affected by shipping cage impacts, because only barrier wire mesh, not pallets, impact the cask with negligible impact force. Ground impact forces react to both the shipping cage and cask impact forces; however, the shipping cage and ground forces affect opposite impact limiters and are not in phase. In addition, the foam impacted by the shipping cage is less compressed than the foam impacted by the cask, and is thereby softer. The LIBRA-AGS dynamic response analysis program is used to determine the shipping cage impact forces, and the AGS analyses take into account both the force phases and foam stiffness properties. The increases in ground impact forces, due to the shipping cage impacts, are determined as fractions of cask impact forces and applied as force factors, fP. Table 2-46 lists the shipping cage used in the impact analyses. Analyses results that include the shipping cage in the 30-ft. drops are provided in Appendix 2.12.11.

Table 2-46. Shipping Cage Weights Used in LIBRA-AGS Dynamic Response Analyses Model Shipping Cage Weight (lbs.)

AOS-025 55.0 AOS-050 240.0 AOS-100 1,500.0

2-138 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-66. Side Impact Slap-Down Analysis

Radioactive Material Transport Packaging System Safety Analysis Report 2-139 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1.5.2.1.1 Cask Impact Loads - Model AOS-025 Table 2-47 presents the Model AOS-025 impact loads determined in the impact limiter analyses, and the corresponding cask stress analysis loads. The actual loads and accelerations applied in Model AOS-025 cask stress analyses are presented in Table 2-48. Table 2-48 also presents equilibrium checks.

where:

fT

=

Temperature load factor fS

=

Slap-down load factor fG

=

Geometric load factor fP

=

Shipping cage load factor f

=

Total load factor, f = fT

  • fS
  • fG
  • fP I

=

Impact force from drop analysis load-displacement curve P

=

Drop analysis impact load, P = f

  • I Table 2-47. Loads and Accelerations Determined in Drop Analysis Impact - Model AOS-025 Load Casea
a. Subscripts x and y designate components of the loading.

fT fS fG fP f

I (lbs.)

P (lbs.)

301 1.0 1.0 1.0 1.05 1.05 1.34 x 105 1.40 x 105 302 1.0 1.2 0.5 1.00 0.60 1.80 x 105 1.08 x 105 303x 1.0 1.0 0.5 1.11 0.56 9.33 x 104 5.22 x 104 303y 1.0 1.0 0.5 1.11 0.56 1.21 x 105 6.78 x 104 304 1.4 1.0 1.0 1.05 1.47 1.34 x 105 1.97 x 105 305 1.4 1.2 0.5 1.00 0.84 1.80 x 105 1.51 x 105 306x 1.4 1.0 0.5 1.11 0.78 9.33 x 104 7.28 x 104 306y 1.4 1.0 0.5 1.11 0.78 1.21 x 105 9.44 x 104

2-140 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) where:

P'

=

Applied impact force A'

=

Applied body acceleration M

=

FEA cask model weight R

=

Total reaction force from FEM cask analysis, R = P' - A'

  • M Table 2-48. Loads and Accelerations Applied in Cask Stress Analyses - Model AOS-025 Load Casea
a. Subscripts x and y designate components of the loading.

P' (lbs.)

A' (g)

M (lbs.)

R (lbs.)

R/P' 301 2.08 x 105 1,779.5 117.17 24.2 0.00 302 1.08 x 105 1,865 57.91 20.3 0.00 303x 5.36 x 104 925.4 57.91 3.2 0.00 303y 6.96 x 104 1,201.4 57.91 2.7 0.00 304 2.90 x 105 2,470.9 117.17 9.2 0.00 305 1.51 x 105 2,611 57.91 28.4 0.00 306x 7.50 x 104 1,295.6 57.91 6.8 0.00 306y 9.74 x 104 1,682 57.91 6.3 0.00

Radioactive Material Transport Packaging System Safety Analysis Report 2-141 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1.5.2.1.2 Cask Impact Loads - Model AOS-050 Table 2-49 presents the Model AOS-050 impact loads determined in the impact limiter analyses, and the corresponding cask stress analysis loads. The actual loads and accelerations applied in Model AOS-050 cask stress analyses are presented in Table 2-50. Table 2-50 also presents equilibrium checks.

where:

fT

=

Temperature load factor fS

=

Slap-down load factor fG

=

Geometric load factor fP

=

Shipping cage load factor f

=

Total load factor, f = fT

  • fS
  • fG
  • fP I

=

Impact force from drop analysis load-displacement curve P

=

Drop analysis impact load, P = f

  • I Table 2-49. Loads Determined in Drop Impact Analyses - Model AOS-050 Load Casea
a. Subscripts x and y designate components of the loading.

fT fS fG fP f

I (lbs.)

P (lbs.)

301 1.0 1.0 1.0 1.06 1.06 3.50 x 105 3.71 x 105 302 1.0 1.2 0.5 1.00 0.60 3.30 x 105 1.98 x 105 303x 1.0 1.0 0.5 1.06 0.53 1.54 x 105 0.82 x 105 303y 1.0 1.0 0.5 1.06 0.53 1.97 x 105 1.04 x 105 304 1.4 1.0 1.0 1.06 1.48 3.50 x 105 5.18 x 105 305 1.4 1.2 0.5 1.00 0.84 3.30 x 105 2.77 x 105 306x 1.4 1.0 0.5 1.06 0.74 1.54 x 105 1.14 x 105 306y 1.4 1.0 0.5 1.06 0.74 1.97 x 105 1.46 x 105

2-142 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) where:

P'

=

Applied impact force A'

=

Applied body acceleration M

=

FEA cask model weight R

=

Total reaction force from FEM cask analysis, R = P' - A'

  • M Table 2-50. Loads and Accelerations Applied in Cask Stress Analyses - Model AOS-050 Load Casea
a. Subscripts x and y designate components of the loading.

P' (lbs.)

A' (g)

M (lbs.)

R (lbs.)

R/P' 301 3.85 x 105 410.9 932 109.6 0.00 302 1.98 x 105 427.4 463.3 19.0 0.00 303x 0.85 x 105 182.8 463.3 13.6 0.00 303y 1.08 x 105 231.2 463.3 286.9 0.00 304 5.31 x 105 566.2 932 60.4 0.00 305 2.77 x 105 598.4 463.3 9.4 0.00 306x 1.19 x 105 256.0 463.3 42.9 0.00 306y 1.51 x 105 325.8 463.3 412.1 0.00

Radioactive Material Transport Packaging System Safety Analysis Report 2-143 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.1.5.2.1.3 Cask Impact Loads - Model AOS-100 Table 2-51 presents the Model AOS-100 impact loads determined in the impact limiter analyses, and the corresponding cask stress analysis loads. The actual loads and accelerations applied in Model AOS-100 cask stress analyses are presented in Table 2-52. Table 2-52 also presents equilibrium checks.

where:

fT

=

Temperature load factor fS

=

Slap-down load factor fG

=

Geometric load factor fP

=

Shipping cage load factor f

=

Total load factor, f = fT

  • fS
  • fG
  • fP I

=

Impact force from drop analysis load-displacement curve P

=

Drop analysis impact load, P = f

  • I Table 2-51. Loads Determined in Drop Analysis - Model AOS-100 Load Casea
a. Subscripts x and y designate components of the loading.

fT fS fG fP f

I (lbs.)

P (lbs.)

301 1.0 1.0 1.0 1.04 1.040 1.42 x 106 1.48 x 106 302 1.0 1.2 0.5 1.00 0.600 1.36 x 106 8.16 x 105 303x 1.0 1.0 0.5 1.05 0.525 6.25 x 105 3.28 x 105 303y 1.0 1.0 0.5 1.05 0.525 8.05 x 105 4.23 x 105 304 1.4 1.0 1.0 1.04 1.456 1.42 x 106 2.07 x 106 305 1.4 1.2 0.5 1.00 0.840 1.36 x 106 1.14 x 106 306x 1.4 1.0 0.5 1.05 0.735 6.25 x 105 4.59 x 105 306y 1.4 1.0 0.5 1.05 0.735 8.05 x 105 5.92 x 105

2-144 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) where:

P'

=

Applied impact force A'

=

Applied body acceleration M

=

FEA cask model weight R

=

Total reaction force from FEM cask analysis, R = P' - A'

  • M Table 2-52. Loads and Accelerations Applied in Cask Stress Analyses - Model AOS-100 Load Casea
a. Subscripts x and y designate components of the loading.

P' (lbs.)

A' (g)

M (lbs.)

R (lbs.)

R / P' 301 1.48 x 106 197.0 7,498 2.14 x 103 0.00 302 8.16 x 105 220.2 3,706 0.29 x 103 0.00 303x 3.54 x 105 95.5 3,706 263.9 0.00 303y 4.54 x 105 122.4 3,706 315.9 0.00 304 2.07 x 106 276.1 7,498 863.9 0.00 305 1.14 x 106 307.6 3,706 4.61 x 103 0.00 306x 4.96 x 105 117.1 3,706 214.0 0.00 306y 6.35 x 105 154.1 3,706 384.8 0.00

Radioactive Material Transport Packaging System Safety Analysis Report 2-145 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.2 Crush The compression load of 5 times (5x) the cask weight, Load Case 215, is analyzed using the 2D model. The compression force is applied to the top of the cask, as a pressure loading using the LE -4a load function.

2.7.3 Puncture The cask component of the AOS Transport Packaging System is evaluated for accidental drops in Load Case 311. The Model AOS-025, AOS-050, and AOS-100 transport packages are analyzed for 121.92-cm (4-ft.) drops onto a rod with a 15 cm (6 in.) diameter. The orientation selected for the drop is Head-On, impacting the package concentric with its vertical center line. This orientation is selected because at this point, the impact limiter has the least thickness. Because the cask/cask lid seal joint is recessed into the cask body and also covered by the impact limiter structure, there is no damage resulting from Free drop of Crush events.

Figure 2-67 illustrates the cask FEA model for a puncture drop. The impacted bar is modeled as fixed points, and the cask is given an initial velocity corresponding to the free-drop height. Figure 2-67 also illustrates the stress state at the time of maximum displacement, at the monitored node used for stress evaluation. Maximum cask weights are used in the Puncture analyses.

a. Ibid (refer to previous LIBRA LE -4 footnote a).

2-146 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 2-67. FEA Model of Puncture Drop

Radioactive Material Transport Packaging System Safety Analysis Report 2-147 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.4 Thermal The Fire condition is analyzed in Section 3.4, Thermal Evaluation under Hypothetical Accident Conditions. In the following paragraphs, maximum values of temperature and pressure are provided for all AOS Transport Packaging System models. In addition, Load Cases representing the Fire condition, at 0.5-hr. intervals throughout the Fire event, are identified. The resulting stresses are provided in Paragraph 2.7.4.4.

2.7.4.1 Summary of Pressures and Temperatures Table 2-53 presents the maximum temperatures, throughout the transport package, resulting from the Fire condition. The structural analyses are applied the temperature field generated by the thermal analysis, to determine the thermal stresses. Table 2-54 presents the pressure corresponding to the maximum temperature for each transport package model. This pressure value is based upon air at 100% relative humidity occupying the entire cavity volume. These pressures do not exceed the design pressure, which is also listed in Table 2-54. Therefore, the transport package can withstand pressures and temperatures in excess of those encountered in the Fire condition.

Pressure-related Load Cases 201 through 204 are analyzed by the 2D cask model. Design pressure, specific for each transport package model, is applied to the models inside cask cavity wall or cask outside surface. The LIBRA LE -4a loading function is used to apply pressure loads. This function generates nodal forces in 2D models due to surface tractions along edge nodal lines. The nodal lines are defined by terminal nodes.

a. The LIBRA programs LE feature defines several types of edge and surface loadings. The first entry is a negative integer that distinguishes the type of loading. The types of loadings and nodal specifications are listed below, with former record types in parentheses.

Options Available when Applying the LE Command Type General loading on nodes specified by numbering sequence.

Type General loading on arc defined by control points (LE1).

Type Surface pressure on arc defined by control points (LEP).

Type Linearly varying pressure on line specified by end nodes.

Type Linearly varying harmonic pressure on 3D model generated from a 2D model.

Further Details for Types -4 and -5 Type This command generates nodal loads corresponding to linearly varying surface tractions along a line on a 2D model. The line is specified by the two (2) terminal nodes, and loads are applied to all nodes within a specified distance of the line. The linearly varying pressure is specified by the terminal values.

Type This command generates nodal loads corresponding to surface tractions over a 3D model generated from an axisymmetric (2D) model. The tractions may vary linearly along a radial line, and circumferentially as a Fourier harmonic. The loaded nodes are identified by specifying the two (2) terminal nodes on the zero meridian. The linearly varying pressure is specified by the corresponding terminal values on the zero meridian.

2-148 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-53. Temperature Summary of Fire Condition - All Models Component Maximum Temperatures, by Model AOS-025A AOS-050A AOS-100A AOS-100A-S AOS-100B

°C

°F

°C

°F

°C

°F

°C

°F Cask Cavity 136 277 259 499 246 476 241 467 Shielding Material 135 276 262 504 246 475 242 467 Cask Lid Seal Area 134 274 223 434 207 404 204 399 Cask Vent Port 134 274 225 437 208 407 206 403 Cask Drain Port 135 276 227 440 210 410 207 405 Test Port 134 274 223 433 206 402 203 397 Cask Vent Port Pipe Plug 134 274 225 437 209 407 206 402 Cask Drain Port Pipe Plug 135 276 227 441 211 411 208 406 Cask Vent Port Conical Seal 134 274 224 435 207 405 205 400 Cask Drain Port Conical Seal 135 276 224 436 208 407 206 402 Cask Outside Surface 145 294 414 777 463 866 463 866 Table 2-54. Maximum Cask Cavity Pressure Due to Fire Condition - All Models Model Temperaturea

a. Temperature listed is the maximum value obtained throughout the Fire event.

Pressureb

b. Pressure calculation is based upon the ideal gas law illustrated in Table 4-6, Maximum Cask Cavity Pressure Due to Normal Conditions of Transport - All Models, footnote a.

Design Pressurec c.

Model AOS-100 transport package - Pressure value is based upon projected operating conditions.

°C

°F kPa psia kPa psia AOS-025A 136 277 139 20 207 30 AOS-050A 259 499 181 26 414 60 AOS-100A AOS-100A-S 246 476 177 26 1,930 280 AOS-100B 241 467 175 25 1,930 280

Radioactive Material Transport Packaging System Safety Analysis Report 2-149 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.4.2 Differential Thermal Expansion Thermal stresses and deformations due to thermal load cases and load combination specified in Reference [2.4] are determined from LIBRA Finite Element analyses, applying the 2D model shown in Figure 2-6. Stresses are calculated, combined and evaluated, as described in Paragraph 2.7.4.3.

2.7.4.3 Stress Calculations Stress calculations are calculated using the LIBRA Finite Element analysis program. The models used in the finite element stress analyses are shown in Figure 2-6 and Figure 2-7. Membrane and bending stresses are calculated at the 22 model cross-sections shown in Figure 2-9. Stresses are calculated for the individual Hypothetical Accident Load Combinations specified in Reference [2.4]. The Load Cases specified in Reference [2.3], and the corresponding analysis Load Case numbers, are listed in Table 2-4.

Each of the 22 cross-sections at which stresses are evaluated involve a number of elements. The elements comprising the cross-sections are listed in Table 2-4. For each cross-section and Load Case, axial, shear, and bending stress resultants are determined by integrating element stresses over the cross-section. Membrane and bending stresses are then determined from the stress resultants and cross-section area properties.

The individual Load Case stresses at the 22 cross-sections shown are combined, according to the Load Combinations specified in Reference [2.4]. The applicable Load Combinations specified in Reference [2.4]

are listed in Table 2-5, along with analysis Load Combination numbers. The membrane and bending stresses combined according to Reference [2.4] are listed in Paragraph 2.7.4.4 for Hypothetical Accident conditions of transport.

The combined membrane and bending stresses are evaluated for Margins of Safety (MS), according to the Design Criteria specified in Reference [2.3]. Paragraph 2.7.8.1 provides the minimum Margin of Safety (MS) obtained for each Load Combination and System model, under Hypothetical Accident conditions of transport.

2-150 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.4.4 Comparison with Allowable Stresses Table 2-55 and Table 2-56 identify the particular table in which the resulting stresses are reported for each AOS Transport Packaging System model, for all Hypothetical Accident conditions of transport Load Cases and Load Combinations, respectively. The referenced tables for each model are located in Appendix 2.12.2, Structural Evaluation Results - Models AOS-025, AOS-050, and AOS-100, within their respective paragraphs.

Table 2-55. Load Cases Associated with Thermal Stresses under Hypothetical Accident Conditions of Transport - All Models Load Case Description Data, by Model AOS-025A AOS-050A AOS-100A AOS-100A-S AOS-100B 111 Fire at 30 Minutes, 1,475°F Ambient, Maximum Decay Heat Table 2-105 Table 2-174 Table 2-242 Table 2-310 112 Post Fire at 60 Minutes, 100°F, Maximum Decay Heat, Maximum Insolation Table 2-106 Table 2-175 Table 2-243 Table 2-311 Post Fire at 90 Minutes, 100°F, Maximum Decay Heat, Maximum Insolation Table 2-107 Table 2-176 Table 2-244 Table 2-312 Post Fire at 120 Minutes, 100°F, Maximum Decay Heat, Maximum Insolation Table 2-108 Table 2-177 Table 2-245 Table 2-313 Post Fire at 150 Minutes, 100°F, Maximum Decay Heat, Maximum Insolation Table 2-109 Table 2-178 Table 2-246 Table 2-314 Post Fire at 180 Minutes, 100°F, Maximum Decay Heat, Maximum Insolation Table 2-110 Table 2-179 Table 2-247 Table 2-315

Radioactive Material Transport Packaging System Safety Analysis Report 2-151 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-56. Load Combinations Associated with Thermal Stresses under Hypothetical Accident Conditions of Transport - All Models Load Combinations Load Cases Description Data, by Model AOS-025A AOS-050A AOS-100A AOS-100A-S AOS-100B 350 111, 201, 211 Fire at 30 Minutes Table 2-127 Table 2-196 Table 2-264 Table 2-332 351 112, 201, 211 Post Fire at 60 Minutes Table 2-128 Table 2-197 Table 2-265 Table 2-333 352 Post Fire at 90 Minutes Table 2-129 Table 2-198 Table 2-266 Table 2-334 353 Post Fire at 120 Minutes Table 2-130 Table 2-199 Table 2-267 Table 2-335 354 Post Fire at 150 Minutes Table 2-131 Table 2-200 Table 2-268 Table 2-336 355 Post Fire at 180 Minutes Table 2-132 Table 2-201 Table 2-269 Table 2-337

2-152 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.5 Immersion - Fissile Material Not applicable. Fissile material is not an authorized content for the AOS Transport Packaging System.

2.7.6 Immersion - All Packages This condition is less demanding to the transport packages than the Deep Water Immersion condition, and is therefore covered by the Deep Water condition. All AOS Transport Packaging System models are analyzed to the Deep Water condition and meet the performance requirements.

2.7.7 Deep Water Immersion Test (for Type B Packages Containing More than 105 A2)

A pressure load of 2 MPa (290 psia) is applied to the cask component of the AOS Transport Packaging System. This condition, represented by Load Case 204, is analyzed by the use of a 2D cask model.

Pressure is applied to the model outside the cask surface. The LIBRA LE -4a loading function is used to apply pressure loads. This function generates nodal forces in 2D models due to surface tractions along edge nodal lines. Terminal nodes define the nodal lines.

Load Case 204 information is presented in Table 2-57. The referenced tables for each model are located in Appendix 2.12.2, Structural Evaluation Results - Models AOS-025, AOS-050, and AOS-100, within their respective paragraphs.

a. Ibid (refer to previous LIBRA LE -4 footnote a).

Table 2-57. Stresses Resulting from Additional Increased External Pressure under Hypothetical Accident Conditions of Transport - All Models Load Case Description Data, by Model AOS-025A AOS-050A AOS-100A AOS-100A-S AOS-100B 204 Additional Increased External Pressure, 2 MPa (290 psia)

Table 2-75 Table 2-144 Table 2-213 Table 2-281

Radioactive Material Transport Packaging System Safety Analysis Report 2-153 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.8 Summary of Damages The evaluation presented in this subsection (Section 2.7, Hypothetical Accident Conditions) demonstrates the ability of the AOS Transport Packaging System to meet the Hypothetical Accident conditions of transport specified in References [2.1] and [2.2]. All damage is confined to the impact limiter component, as designed. The integrity of the containment system is not affected by these events.

The cask drain port, cask vent port, and test port also do not suffer any damage, as a consequence of Hypothetical Accident conditions of transport. These cask component features are well-protected by the impact limiters inside shell. The results of the Free-Drop test verify that the shell does not suffer damage that could negatively impact these features, protecting them from direct impact. Also, the analytical evaluation shows that these ports are located within areas of low-stress intensity, for all Hypothetical Accident conditions of transport.

Table 2-58 and Table 2-59 identify the particular table in which the resulting stresses are reported for each AOS Transport Packaging System model, for all Hypothetical Accident conditions of transport Load Cases and Load Combinations, respectively. Paragraph 2.7.8.1 provides the minimum Margin of Safety (MS) obtained for each Load Combination and System model, under Hypothetical Accident conditions of transport.

This data shows that the AOS Transport Packaging System has the capacity to endure all Hypothetical Accident conditions of transport without affecting its ability to contain and to shield the radioactive material payload from undue risk to the public.

2-154 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-58. Load Cases Associated with Allowable Stresses under Hypothetical Accident Conditions of Transport - All Models Load Case Description Data, by Model AOS-025A AOS-050A AOS-100A AOS-100A-S AOS-100B 111 Fire at 30 Minutes, 1,475°F Ambient, Maximum Decay Heat Table 2-105 Table 2-174 Table 2-242 Table 2-310 112 Post Fire at 60 Minutes, 100°F, Maximum Decay Heat, Maximum Insolation Table 2-106 Table 2-175 Table 2-243 Table 2-311 Post Fire at 90 Minutes, 100°F, Maximum Decay Heat, Maximum Insolation Table 2-107 Table 2-176 Table 2-244 Table 2-312 Post Fire at 120 Minutes, 100°F, Maximum Decay Heat, Maximum Insolation Table 2-108 Table 2-177 Table 2-245 Table 2-313 Post Fire at 150 Minutes, 100°F, Maximum Decay Heat, Maximum Insolation Table 2-109 Table 2-178 Table 2-246 Table 2-314 Post Fire at 180 Minutes, 100°F, Maximum Decay Heat, Maximum Insolation Table 2-110 Table 2-179 Table 2-247 Table 2-315 301 30-ft. Head-On Drop Table 2-111 Table 2-180 Table 2-248 Table 2-316 302 30-ft. Side Drop + Slap-Down Table 2-112 Table 2-181 Table 2-249 Table 2-317 303 30-ft. Cg/Corner Drop Table 2-113 Table 2-182 Table 2-250 Table 2-318 304 30-ft. Head-On Drop at -40°F, Low Temperature Table 2-114 Table 2-183 Table 2-251 Table 2-319 305 30-ft. Side Drop + Slap-Down at -40°F, Low Temperature Table 2-115 Table 2-184 Table 2-252 Table 2-320 306 30-ft. Cg/Corner Drop at -40°F, Low Temperature Table 2-116 Table 2-185 Table 2-253 Table 2-321 311 4-ft. Drop onto Rod Table 2-117 Table 2-186 Table 2-254 Table 2-322

Radioactive Material Transport Packaging System Safety Analysis Report 2-155 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-59. Load Combinations Associated with Allowable Stresses under Hypothetical Accident Conditions of Transport - All Models Load Combinations Load Cases Description Data, by Model AOS-025A AOS-050A AOS-100A AOS-100A-S AOS-100B 301 301, 102, 201, 211 Head-On Drop Orientation Table 2-118 Table 2-187 Table 2-255 Table 2-323 302 302, 102, 201, 211 Side Drop Orientation Table 2-119 Table 2-188 Table 2-256 Table 2-324 303 303, 102, 201, 211 Cg/Corner Drop Orientation Table 2-120 Table 2-189 Table 2-257 Table 2-325 304 304, 105, 202, 211 Head-On Drop Orientation at -

40°F, Cold Environment Table 2-121 Table 2-190 Table 2-258 Table 2-326 305 305, 105, 202, 211 Side Drop Orientation at -40°F, Cold Environment Table 2-122 Table 2-191 Table 2-259 Table 2-327 306 306, 105, 202, 211 Cg/Corner Drop Orientation at -40°F, Cold Environment Table 2-123 Table 2-192 Table 2-260 Table 2-328 310 204, 101, 211 Additional Increased External Pressure (290 psi)

Table 2-124 Table 2-193 Table 2-261 Table 2-329 311 311, 101, 201, 211 4-ft. Drop onto Rod Table 2-125 Table 2-194 Table 2-262 Table 2-330 312 311, 104, 201, 211 4-ft. Drop onto Rod at -40°F, Cold Environment Table 2-126 Table 2-195 Table 2-263 Table 2-331 350 111, 201, 211 Fire at 30 Minutes Table 2-127 Table 2-196 Table 2-264 Table 2-332 351 112, 201, 211 Post Fire at 60 Minutes Table 2-128 Table 2-197 Table 2-265 Table 2-333 352 Post Fire at 90 Minutes Table 2-129 Table 2-198 Table 2-266 Table 2-334 353 Post Fire at 120 Minutes Table 2-130 Table 2-199 Table 2-267 Table 2-335 354 Post Fire at 150 Minutes Table 2-131 Table 2-200 Table 2-268 Table 2-336 355 Post Fire at 180 Minutes Table 2-132 Table 2-201 Table 2-269 Table 2-337

2-156 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.7.8.1 Minimum Margins of Safety Table 2-60 through Table 2-63 provide the Minimum Margin of Safety (MS) obtained for each Load Combination and System model, under Hypothetical Accident conditions of transport.

Table 2-60. Min MS for Hypothetical Accident Conditions of Transport - Model AOS-025A Ld_Cmb Load_Cases Min_MS Loc Str_Cmb 301 301 102 201 211 0 2.457E+00 4 Pm+Pb 302 302 102 201 211 0 7.184E+00 19 Pm 303 303 102 201 211 0 4.434E+00 4 Pm 304 304 105 202 211 0 1.833E+00 4 Pm+Pb 305 305 105 202 211 0 5.825E+00 19 Pm 306 306 105 202 211 0 3.265E+00 4 Pm 310 204 101 211 0 0 1.138E+00 4 Pm+Pb 311 311 101 201 211 0 2.782E+00 15 Pm 312 311 104 201 211 0 2.782E+00 15 Pm 350 111 201 211 0 0 1.365E+01 20 Pm+Pb 351 112 201 211 0 0 1.365E+01 20 Pm+Pb 352 113 201 211 0 0 1.365E+01 20 Pm+Pb 353 114 201 211 0 0 1.365E+01 20 Pm+Pb 354 115 201 211 0 0 1.365E+01 20 Pm+Pb 355 116 201 211 0 0 1.365E+01 20 Pm+Pb Table 2-61. Min MS for Hypothetical Accident Conditions of Transport - Model AOS-050A Ld_Cmb Load_Cases Min_MS Loc Str_Cmb 301 301 102 201 211 0 3.771E+00 4 Pm+Pb 302 302 102 201 211 0 7.094E+00 1 Pm+Pb 303 303 102 201 211 0 7.457E+00 4 Pm+Pb 304 304 105 202 211 0 3.103E+00 4 Pm+Pb 305 305 105 202 211 0 5.793E+00 1 Pm+Pb 306 306 105 202 211 0 7.087E+00 4 Pm+Pb 310 204 101 211 0 0 2.815E+00 4 Pm+Pb 311 311 101 201 211 0 3.697E-01 15 Pm 312 311 104 201 211 0 4.167E-01 15 Pm 350 111 201 211 0 0 1.407E+01 4 Pm+Pb 351 112 201 211 0 0 1.257E+01 4 Pm+Pb 352 113 201 211 0 0 1.257E+01 4 Pm+Pb 353 114 201 211 0 0 1.257E+01 4 Pm+Pb 354 115 201 211 0 0 1.257E+01 4 Pm+Pb 355 116 201 211 0 0 1.257E+01 4 Pm+Pb

Radioactive Material Transport Packaging System Safety Analysis Report 2-157 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 2-62. Min MS for Hypothetical Accident Conditions of Transport -

Models AOS-100A and AOS-100A-S Ld_Cmb Load_Cases Min_MS Loc Str_Cmb 301 301 102 201 211 0 1.525E+00 4 Pm+Pb 302 302 102 201 211 0 2.843E+00 4 Pm+Pb 303 303 102 201 211 0 2.665E+00 4 Pm+Pb 304 304 105 202 211 0 2.463E+00 4 Pm+Pb 305 305 105 202 211 0 7.547E+00 1 Pm 306 306 105 202 211 0 7.608E+00 4 Pm 310 204 101 211 0 0 2.724E+00 4 Pm+Pb 311 311 101 201 211 0 2.703E-01 15 Pm 312 311 104 201 211 0 3.138E-01 15 Pm 350 111 201 211 0 0 3.854E+00 4 Pm+Pb 351 112 201 211 0 0 3.524E+00 4 Pm+Pb 352 113 201 211 0 0 3.524E+00 4 Pm+Pb 353 114 201 211 0 0 3.524E+00 4 Pm+Pb 354 115 201 211 0 0 3.524E+00 4 Pm+Pb Table 2-63. Min MS for Hypothetical Accident Conditions of Transport - Model AOS-100B Ld_Cmb Load_Cases Min_MS Loc Str_Cmb 301 301 102 201 211 0 1.525E+00 4 Pm+Pb 302 302 102 201 211 0 2.843E+00 4 Pm+Pb 303 303 102 201 211 0 2.665E+00 4 Pm+Pb 304 304 105 202 211 0 2.463E+00 4 Pm+Pb 305 305 105 202 211 0 7.547E+00 1 Pm 306 306 105 202 211 0 7.608E+00 4 Pm 310 204 101 211 0 0 2.724E+00 4 Pm+Pb 311 311 101 201 211 0 2.703E-01 15 Pm 312 311 104 201 211 0 3.138E-01 15 Pm 350 111 201 211 0 0 3.854E+00 4 Pm+Pb 351 112 201 211 0 0 3.524E+00 4 Pm+Pb 352 113 201 211 0 0 3.524E+00 4 Pm+Pb 353 114 201 211 0 0 3.524E+00 4 Pm+Pb 354 115 201 211 0 0 3.524E+00 4 Pm+Pb

2-158 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 2.8 ACCIDENT CONDITIONS FOR AIR TRANSPORT OF PLUTONIUM Not applicable. Plutonium is not an authorized content for the AOS Transport Packaging System.

2.9 ACCIDENT CONDITIONS FOR FISSILE MATERIAL PACKAGE FOR AIR TRANSPORT Not applicable. Fissile material is not an authorized content for the AOS Transport Packaging System.

2.10 SPECIAL FORM The AOS Transport Packaging system is authorized to ship both Normal and Special form material, as described in Subsection 1.2.2, Contents.

2.11 FUEL RODS Not applicable. This section does not apply to the AOS Transport Packaging System.

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