ML20244E527

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Summary of 890525 Meeting W/Westinghouse,Eg&G,Doe & Weston in Rockville,Md Re Titan Spent Fuel Shipping Cask
ML20244E527
Person / Time
Site: 07109229
Issue date: 06/15/1989
From: Osgood N
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 8906200380
Download: ML20244E527 (2)


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r lt-MEMORANDUM FOR: The Files R.

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Nancy L. 0sgood Transportation Branch, NMSS l,

SUBJECT:

MEETING

SUMMARY

CONCERNING WESTINGHOUSE TITAN TRUCK CASK Attenddes

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j WESTINGHOUSE EG&G

-NRC Bill ~ Boyd.

Ira Hall Ross Chappell Bala R. Nair.=

K. Pat.Lange Henry Lee.

Wayne Severson Curt Lindner i

Nancy Osgood P

Carl Withee Li Yang DOE LWESTON Bill Lake Meraj Rahimi Introduction-A meeting was held at the request of Westinghouse Electric Corporation (W) at Rockville, Maryland, on May 25, 1989, concerning the Titan spent fuel shipping cask. This cask is being developed for DOE for truck shipments under the Nuclear Waste Policy' Act.

Discussion General The Titan spent fuel cask is a cylindrical truck cask with impact limiters on each end. The cask body will be made of titanium alloy. Depleted uranium and solid borosilicone are used for gamma and neutron shielding.

Interchangeable fuel baskets are stainless steel with boral plates, and will hold 3 PWR or 7

.DWR assemblies.

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a Impact Limiters The original concept o? aluminum toroidal impact limiters for the Titan cas'k was found to be impractical. The current design includes aluminum honeycomb impact limiters bolted to both ends of the cask. Testing of the impact limiters will include materials tests, testing of the glue used to hold sections together, half-scale model load-deflection tests with a cask body mockup, and the scale model cask tests.

Fuel Basket The fuel baskets are stainless steel and incorporate support ribs to eliminate buckling due to normal or accident transport conditions. Boral plates are used for neutron poison. Criticality analyses show that an infinite array of casks remains subcritical, even assuming water inleakage. The snalyses assumed fresh fuel with 4.5 w/o enrichment.

Initial analyses were done assuming that the borosilicone neutron shield remains intact after the hypothetical accident sequence. The possibility of loss of this shield material due to melting during the fire test will be considered.

Titanium Alloy W has requested that the titanium material be approved by ASME for Section III NB structures. Material properties are being evaluated for the range of temperatures the cask may experience. Welding and NDE procedures will be developed. An independent group of experts will evaluate the suitability of titanium for transport casks. They will evaluate the material in the context of NRC philosophy of brittle fracture. W expects that materials tests will show that this titanium alloy is similar to stainless steel in fracture toughness.

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Tg Nancy L. Osgood Transportation Branch, NMSS DISTRIBUTION:

Meeting Attendees Meeting Notebook F/C._,.NRC PDR SGTB r/f HMSS r/f EEaston CMacDonald

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