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Title: Status of spent-fuel shipping cask development

Abstract

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

Citation Formats

Hall, I.K., and Hinschberger, T.S. Status of spent-fuel shipping cask development. United States: N. p., 1989. Web.
Hall, I.K., & Hinschberger, T.S. Status of spent-fuel shipping cask development. United States.
Hall, I.K., and Hinschberger, T.S. 1989. "Status of spent-fuel shipping cask development". United States. doi:.
@article{osti_6815828,
title = {Status of spent-fuel shipping cask development},
author = {Hall, I.K. and Hinschberger, T.S.},
abstractNote = {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. Reducing turnaround time promotes reduced radiation exposure to occupational workers and improves cask utilization efficiency.},
doi = {},
journal = {Transactions of the American Nuclear Society; (USA)},
number = ,
volume = 60,
place = {United States},
year = 1989,
month = 1
}

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  • The Nuclear Waste Policy Act of 1982 (NWPA) authorized the US Department of Energy (DOE) to establish a national system for the disposal of spent nuclear fuel and high-level radioactive waste from commercial power generation, and established the Office of Civilian Radioactive Waste Management (OCRWM) within the DOE-Headquarters (DOE-HQ) to carry out these duties. A 1985 presidential decision added the disposal of high-level radioactive waste generated by defense programs to the national disposal system. A primary element of the disposal program is the development and operation of a transportation system to move the waste from its present locations to themore » facilities that will be included in the waste management system. The primary type of disposal facility to be established is a geologic repository; a Monitored Retrievable Storage (MRS) facility may also be included as an intermediate step in the nuclear waste disposal process. This paper focuses on the progress and status of one facet of the transportation program--the development of a family of shipping casks for transporting spent fuel from nuclear power reactor sites to the repository of MRS facility.« less
  • The purpose of the Cask Systems Development Program (CSDP) is to develop a variety of cask system which 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.
  • Several new-generation shipping cask systems are being developed for safe and economical transport of commercial spent nuclear fuel and other radioactive wastes from the generating sites to a Federal geologic repository or Monitored Retrievable Storage (MRS) facility. Primary objectives of the from-reactor spent fuel cask development work are: (a) to increase cask payloads by taking advantage of the increased at-reactor storage time under the current spent fuel management scenario, (b) to facilitate more efficient cask handling operations with reduced occupational radiation exposure, and (c) to promote standardization of the physical interfaces between casks and the shipping and receiving facilities. Increasedmore » cask payloads will significantly reduce the number of shipments, with corresponding reductions in transportation costs and risks to transportation workers, cask handling personnel, and the general public.« less
  • Continued public acceptance of commercial nuclear power is contingent to a large degree on the US Department of Energy (DOE) establishing an integrated waste management system for spent nuclear fuel. As part of the from-reactor transportation segment of this system, the B W Fuel Company (BWFC) is under contract to the DOE to develop a spent-fuel cask that is compatible with both rail and barge modes of transportation. Innovative design approaches were the keys to achieving a cask design that maximizes payload capacity and cask performance. The result is the BR-100, a 100-ton rail/barge cask with a capacity of 21more » PWR or 52 BWR ten-year cooled, intact fuel assemblies. 3 figs.« less