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Keywords: spent nuclear fuel
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Proceedings Papers

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A061, July 13–15, 2021
Paper No: PVP2021-64176
... Proceedings of the ASME 2021 Pressure Vessels & Piping Conference PVP2021 July 13-15, 2021, Virtual, Online PVP2021-64176 TECHNICAL BASIS SUMMARY FOR CODE CASE N-860: INSPECTION REQUIREMENTS AND EVALUATION STANDARDS FOR SPENT NUCLEAR FUEL STORAGE AND TRANSPORTATION CONTAINMENT SYSTEMS John E...
Proceedings Papers

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A022, July 13–15, 2021
Paper No: PVP2021-60533
... conditions of transport 30 cm drop acceleration pulse cladding strain stress-strain curve rod-to-rod contact contact pressure spent nuclear fuel nuclear waste management Proceedings of the ASME 2021 Pressure Vessels & Piping Conference PVP2021 July 13-15, 2021, Virtual, Online PVP2021-60533 30 CM...
Proceedings Papers

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A106, August 3, 2020
Paper No: PVP2020-21399
... River National Laboratory Aiken, South Carolina, 29808, USA Myeong-Woo Lee Korea Atomic Energy Research Institute, Daedukdaero 1045, Yuseong-Ku, Daejeon 34057, Republic of Korea ABSTRACT Spent nuclear fuels are stored in dry storage canisters made of austenitic stainless steels. Canisters have...
Proceedings Papers

Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A034, August 3, 2020
Paper No: PVP2020-21083
... tests and the additional calculations by using numerical and analytical methods. transport of radioactive material spent nuclear fuel mechanical and thermal assessment package design MECHANICAL AND THERMAL ASSESSMENT BY BAM OF A NEW PACKAGE DESIGN FOR THE TRANSPORT OF SNF FROM A GERMAN...
Proceedings Papers

Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A054, July 14–19, 2019
Paper No: PVP2019-94055
... Boiler and Pressure Vessel Code Case covering stainless steel canisters. spent nuclear fuel dry cask storage system (DCSS) chloride induced stress corrosion cracking (CISCC) CRACK GROWTH RATE MODEL FOR CISCC OF STAINLESS STEEL CANISTERS John E. Broussard, III, P.E. Dominion Engineering, Inc...
Proceedings Papers

Proc. ASME. PVP2005, Volume 7: Operations, Applications, and Components, 639-648, July 17–21, 2005
Paper No: PVP2005-71743
... the shielding or structural functions, although there has been some minor cracking of the concrete. Concrete nuclear applications spent nuclear fuel VSC-17 storage Proceedings of PVP2005: 2005 ASME Pressure Vessels and Piping Division Conference he the for se ga ap wa as de 15 en aff be KE sto 1...