End Effects in the Criticality Analysis of Burnup Credit Casks
Conference
·
OSTI ID:6625955
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
A study to evaluate the effect of axially dependent burnup on keff has been performed as part of an effort to qualify procedures to be used in establishing burnup credit in shipping cask design and certification. This study was performed using a generic 31-element modular cast-iron cask (wall thickness 33.1 cm) with a 1-cm-thick borated stainless-steel basket for reactivity control. Fuel isotopics used here are those of the 17 ˙ 17 Westinghouse assemblies from the North Anna Unit 1 reactor. Virginia Power (VP) provided detailed spatial isotopics for the fuel assemblies in-core at beginning-of-cycle 5 (BOC-5) as generated from their PDQ analyses. Twenty-two axial planes were defined in the original VP data. The isotopics used in this study were for a 3.41 initial wt % 235U and an average burnup of 31.5 GWd/MTU.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6625955
- Report Number(s):
- CONF-901101--10; ON: DE90012942
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of burnup credit for dry storage casks
Overview of Effects of Burnup Credit on Cask Design
Isotopic Bias and Uncertainty for Burnup Credit Applications
Technical Report
·
Tue Aug 01 00:00:00 EDT 1989
·
OSTI ID:5836504
Overview of Effects of Burnup Credit on Cask Design
Conference
·
Mon Oct 31 23:00:00 EST 1988
·
OSTI ID:7026655
Isotopic Bias and Uncertainty for Burnup Credit Applications
Technical Report
·
Mon Aug 19 00:00:00 EDT 2002
·
OSTI ID:802601
Related Subjects
050900* -- Nuclear Fuels-- Transport
Handling
& Storage
07 ISOTOPE AND RADIATION SOURCES
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420204 -- Engineering-- Shipping Containers
BURNUP
CASKS
CONTAINERS
CRITICALITY
DESIGN
ENERGY SOURCES
FUELS
Isotopics
MATERIALS
NUCLEAR FUELS
Nuclear Criticality Safety Program (NCSP)
REACTOR MATERIALS
SPENT FUEL CASKS
SPENT FUELS
Study
TRANSPORT
Handling
& Storage
07 ISOTOPE AND RADIATION SOURCES
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420204 -- Engineering-- Shipping Containers
BURNUP
CASKS
CONTAINERS
CRITICALITY
DESIGN
ENERGY SOURCES
FUELS
Isotopics
MATERIALS
NUCLEAR FUELS
Nuclear Criticality Safety Program (NCSP)
REACTOR MATERIALS
SPENT FUEL CASKS
SPENT FUELS
Study
TRANSPORT