Nuclear criticality safety studies applicable to spent fuel shipping cask designs and spent fuel storage

Technical Report · Sat Nov 01 00:00:00 EST 1980

DOI:https://doi.org/10.2172/6775746· OSTI ID:6775746

Tang, J. S.

Criticality analyses of water-moderated and reflected arrays of LWR fresh and spent fuel assemblies were carried out in this study. The calculated results indicate that using the assumption of fresh fuel loading in spent fuel shipping cask design leads to assembly spacings which are about twice the spacings of spent fuel loadings. Some shipping cask walls of composite lead and water are more effective neutron reflectors than water of 30.48 cm (12 in).

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6775746
• Report Number(s): ORNL/TM-7403; TRN: 80-019346
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
SPENT FUEL CASKS
CRITICALITY
WATER COOLED REACTORS
FUEL CYCLE
FUEL ASSEMBLIES
LEAD
NEUTRON REFLECTORS
SAFETY
SPENT FUEL ELEMENTS
WATER
CASKS
CONTAINERS
ELEMENTS
FUEL ELEMENTS
HYDROGEN COMPOUNDS
METALS
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTORS
420203* - Engineering- Handling Equipment & Procedures
420204 - Engineering- Shipping Containers
050900 - Nuclear Fuels- Transport
Handling
& Storage