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Title: Status of spent-fuel shipping cask development

The purpose of the Cask Systems Development Program is to develop a variety of cask systems that can safely and economically transport commercial spent fuel and high-level waste from the generating sites to a federal geologic repository or monitored retrievable storage (MRS) facility. This paper is limited to a discussion of the status of from-reactor spent-fuel cask development; future cask development plans include MRS-to-repository casks, specialty casks for nonstandard spent fuel and nonfuel materials, and defense high-level waste casks. Spent-fuel casks must be available in the late 1990s to support the U.S. Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) shipments from utilities. DOE-Idaho, with the support of EG G Idaho, Inc., Sandia National Laboratories, and selected cask developing contractors, has been assigned the responsibility for developing a new generation of cask systems. Four categories of spent fuel casks were initially proposed: (1) legal weight truck (LWT) casks (2) overweight truck (OWT) casks (3) rail/barge (R/B) casks (4) dual purpose (DP) storage/transport casks. Casks are being designed for reduced occupational radiation exposure at the receiving facility by facilitating the use of remote handling equipment. Automation of remote handling systems may be used to reduce cask turnaround time.more » Reducing turnaround time promotes reduced radiation exposure to occupational workers and improves cask utilization efficiency.« less
Authors:
;
Publication Date:
OSTI Identifier:
6815828
Report Number(s):
CONF-891103--
Journal ID: ISSN 0003-018X; CODEN: TANSA; TRN: 90-023045
Resource Type:
Conference
Resource Relation:
Journal Name: Transactions of the American Nuclear Society; (USA); Journal Volume: 60; Conference: Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit, San Francisco, CA (USA), 26-30 Nov 1989
Country of Publication:
United States
Language:
English
Subject:
42 ENGINEERING; SPENT FUEL CASKS; DESIGN; BWR TYPE REACTORS; HIGH-LEVEL RADIOACTIVE WASTES; MONITORED RETRIEVABLE STORAGE; OCCUPATIONAL EXPOSURE; OPTIMIZATION; PUBLIC OPINION; PWR TYPE REACTORS; RADIATION PROTECTION; RADIOACTIVE WASTE FACILITIES; SAFETY; SANDIA LABORATORIES; SLIGHTLY ENRICHED URANIUM; SPECIFICATIONS; SPENT FUELS; TRANSPORT; URANIUM 235; US DOE; VERIFICATION; ACTINIDE ISOTOPES; ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; CASKS; CONTAINERS; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM; EVEN-ODD NUCLEI; FUELS; HEAVY NUCLEI; ISOMERIC TRANSITION ISOTOPES; ISOTOPE ENRICHED MATERIALS; ISOTOPES; MANAGEMENT; MATERIALS; METALS; MINUTES LIVING RADIOISOTOPES; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; NUCLEAR FUELS; NUCLEI; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE STORAGE; RADIOACTIVE WASTES; RADIOISOTOPES; REACTOR MATERIALS; REACTORS; SPENT FUEL STORAGE; STORAGE; URANIUM; URANIUM ISOTOPES; US AEC; US ERDA; US ORGANIZATIONS; WASTE MANAGEMENT; WASTE STORAGE; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES 420204* -- Engineering-- Shipping Containers