Cask Designers Guide: A Guide for the Design, Fabrication, and Operation of Shipping Casks for Nuclear Applications.

Shappert, L.B.

doi:10.2172/4759737

Cited by 9 publications

(6 citation statements)

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“…A safety factor of 3.0 with respect to yield during normal handling at 400 0 C (750 0 F) was adopted as a design criterion. This safety factor is in accordance with recommendations of the cask designers guide (Shappert 1978) for lifting loads applied to shipping containers for nuclear applications. With this safety factor, the design stresses were 50.5 MN/m2 (7320 psi) and 73.0 MN/m2 (10,590 psi), respectively, for 304L stainless steel and Inconel 601.…”

Section: Figure E5 Schematic Diagram Showing Transducers Andsupporting

confidence: 83%

“…It is the objective here to illustrate methods that can ensure that overstress conditions do not occur during handling. The rules given in the cask designer's guide (Shappert 1978) were found to be appropriate for HLW canisters. The main requirement of this guide is that there be a safety factor of 3.0 with respect to yield for static 1.0-g loads.…”

Section: Lifting Stresses On Twist-lock Closuresmentioning

confidence: 99%

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Stress analysis of high-level waste canisters: methods, applications, and design data

Simonen¹,

Slate²

1979

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The Pacific Northwest Laboratory (PNL) is conducting research and development studies on technology for immobilization of nuclear wastes. In this report, an overview of stress analysis methods, structural design procedures, and design data is presented for canisters used to package solidified wastes, particularly borosilicate glass. In addition, waste processing, canister materials, fabrication and inspection methods, and performance testing are summarized. Sources of stress in canisters are lifting and handling loads, internal pressure, hightemperature filling operations, transient heating and cooling, differential thermal expansions of canisters and glass, and impact loadings from low-probability accidents. Results of case studies that illustrate applicable methods of stress analyses are presented for these sources of stress. Existing sections of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code are reviewed and found to be applicable to canister fabrication, but the code does not cover many aspects of canister service loadings. Specialized criteria for minimum wall thicknesses to sustain filling stresses are proposed in this report. Results of a test program to measure the creep strength of candidate canister materials are described. Methods to predict residual stresses in the walls of waste canisters are described; predicted residual stress levels agree with measured stress levels. The consequences of these residual stresses are reviewed, and stress-corrosion cracking is identified as the mode of canister failure affected by residual stresses. Canister-closure design is covered in detail, particularly the welding and inspection of the final closure seal-weld. It is shown that the methods of fracture mechanics and fatiguecrack-growth analyses are valuable tools for evaluating the performance of closure welds in the presence of crack-like defects. Canister performance in process trials at PNL shows the ability of canisters to survive high temperatures and loadings during processing. The results of impact tests at PNL show that a suitably designed canister can sustain severe impacts without loss of integrity • iii

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Section: Figure E5 Schematic Diagram Showing Transducers Andsupporting

confidence: 83%

Section: Lifting Stresses On Twist-lock Closuresmentioning

confidence: 99%

Stress analysis of high-level waste canisters: methods, applications, and design data

Simonen¹,

Slate²

1979

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“…With the greater depth of penetration of the electron-beam weld, rupture that occurred for the TIG weld was avoided. The general lack of resistance of partial penetration welds to impact loadings is described by Shappert (1970).…”

Section: Review Of Closure Conceptsmentioning

confidence: 99%

Stress analysis and testing of the outer capsule design for the Strontium Heat Source Development Program

Simonen¹,

Shippell²,

Atteridge³

1980

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The objective of the Strontium Heat Source Development Program is to 90 obtain the data needed to license SrF^ heat sources-specifically the 90 SrFp capsules produced in the Waste Encapsulation and Storage Facility (WESF) at Hanford. Toward this end, a high integrity outer capsule has 90 been designed to replace the present outer capsule of the WESF SrFp capsule. This report describes the proposed design of a Hastelloy S® outer capsule which features a mechanical interlock type of end closure. Qualification testing requirements are outlined, and stress analyses and developmental tests are described. These tests were performed on AISI-1018 steel stand-in capsules, and included both external pressure and impact tests. The external pressure tests showed that stress calculations seriously overestimated the pressure capability of the outer capsule. Possible reasons for the lack of agreement between the tests and the analyses are evaluated. The stress analyses and test results indicate that the proposed outer capsule will meet the heat source qualification requirements. Future tests will be conducted to experimentally verify that the Hastelloy S outer capsule in an aged condition meets the structural integrity requirements. Hastelloy is a trade name of the Stellite Division, Cabot Corporation.

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“…In a study by Sandia Laboratories, 16 The principles of design of shielded shipping cases (with cooling means) that conform to performance specifications, safety criteria, and other regulations have been summarized by Oak Ridge National Laboratory. 17 The references to internal heat transfer are notable: "Present regulations do not place a limit on the maximum temperature of a spent fuel element during transport. What they do require is that, under normal conditions of transport, no radioactive material be released from the containment vessel.…”

Section: Shipping and Canister Reliabilitymentioning

confidence: 99%

Analysis of factors influencing the reliability of retrievable storage canisters for containment of solid high-level radioactive waste

Mecham¹,

Seefeldt²,

Steindler³

1976

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3.2.4.1. 4.2.4.3. 4.'.4.5. 5.1. 5.2.5.3. to a final disposal facility. 8.1. 8.2. Classification of Alloys According to Cracking Behavior inThe properties of stainless steel type 304L, fission product oxides, calcine, and glass were reviewed, and mechanisms of corrosion were identified and studied. The modes of corrosion important for reliability were stress-cnrrosion cracking, internal pressurisatica of the canister by residual impurities present. intergranular attack at the waste-canister interface, and potential local effects due to migration of fission products.The key role of temperatuwo control throughout canister lifetime is considered, together with interactive effects.Methods of amellorating adveraM effects and ensuring high reliability are id-ntified and described. Conclusions and recoimnnd.:tion are presented.The basic question addressed to this study to the reliability of waste canisters in engineered storage of radioactive waste, ftr omromri were set by the reviewers to establish a concrete vovte. for toe study of reliability.The basic waste package stored to the 5SF to a cylindrical metal tanister.Into which concentrated fi sion product waste is ;haraa . as dry solid osideeither tanular (calcine) or as a vitrif Led mass (by use of silicate additions to form glass). tn this stuay. reliability was defined narrowly to nen the iaberent ability of the canister to rerin intact for the period of storage.If the canister remas intact. the waste is comletely isolated from the bm environment and no leaching or other dispersion practices can take place.We confined our attention to the range of conditions for wbicb Inherent reliability Is expected and did not evaluate the effects of Pearelitability..e., the hasardous consequences of failure of the canister to provide effective contaiment. Our focus on realist ic practical operattoa led us to cosftie our attention to only those abnormal and accident situations that wfre considered In our judgment to be reasonable deprtures f rom normal conditions and therefore reprsentative of the Ioberent reliability of the storage concept.Since safety is. by denities, evaluated to ts;ar of the risk Involved t the consequence. of oearellability of cotainet. we did not directly address safety except to indicate that radioactivity released t the event of canister failure is subject to confitnmet by secondary containmt features of the facility and to control by i onitoring and remedial-action features of the system.Our as was to evaluate reliability in term of current reliability methodology, which has the foray of quant tative syr.t m analysts. As is all engineering concepts, there is a trade-off (explicit or implicit) between cost and reliability. The specifics of the trade-off are. t fat. the definition of current technology. We found that the presise of inAerent reliability of vast. storage t god to :erms of basic feasibility, but that the system design lacks the sort of specificity aod supporttg performance data needed to establish reliability quantitatively and t terns clearl...

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Cask Designers Guide: A Guide for the Design, Fabrication, and Operation of Shipping Casks for Nuclear Applications.

Cited by 9 publications

References 0 publications

Stress analysis of high-level waste canisters: methods, applications, and design data

Stress analysis of high-level waste canisters: methods, applications, and design data

Stress analysis and testing of the outer capsule design for the Strontium Heat Source Development Program

Analysis of factors influencing the reliability of retrievable storage canisters for containment of solid high-level radioactive waste

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