Published November 1989 | Version v1
Journal article Metadata-only

Shielding design for spent-fuel shipping in high-capacity truck casks

Creators

  • 1. General Atomics, San Diego, CA (USA)

Description

General Atomics (GA), under contract to the U.S. Department of Energy (DOE), is developing a high-capacity legal-weight truck transportation system for shipment of pressurized water reactor (PWR) and boiling water rector (BWR) spent fuels from commercial nuclear power plants to a repository or monitored retrievable storage facility. The system includes two cask versions optimized for PWR and BWR fuels, respectively. The PWR version carries four fuel assemblies designated the GA-4 cask, and the BWR version accommodates nine fuel assemblies designated the GA-9 cask. This paper presents the shielding aspects of the GA-4 and GA-9 casks

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
60
Series
Trans. Am. Nucl. Soc.
Journal Page Range
525-526
ISSN
0003-018X
CODEN
TANSA

Conference

Title
Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
Dates
26-30 Nov 1989.
Place
San Francisco, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
22090706
Subject category
S42: ENGINEERING; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALARA; BURNUP; BWR TYPE REACTORS; CAPACITY; CASKS; COMPUTER CODES; COST; FUEL ASSEMBLIES; GAMMA TRANSPORT THEORY; GEOMETRY; LIFE CYCLE; MAPS; NEUTRON TRANSPORT; O CODES; OPTIMIZATION; P CODES; PWR TYPE REACTORS; RADIATION DOSES; RADIATION PROTECTION; REGULATIONS; SHIELDING; SPECIFICATIONS; SPENT FUEL STORAGE; T CODES; THRESHOLD DOSE; TRANSPORT; US DOE; US MRS PROJECT
Descriptors DEC
CONTAINERS; ENRICHED URANIUM REACTORS; LAWS; MATHEMATICS; NATIONAL ORGANIZATIONS; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; RADIATION TRANSPORT; REACTORS; STORAGE; THERMAL REACTORS; TRANSPORT THEORY; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-891103--.