Keno V. a Validation of Fuel Pin Experiments

Conference · Sat Nov 14 23:00:00 EST 1987

OSTI ID:6216182

Dyer, H. R. ^[1]; Westfall, R. M. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

This paper describes the results of computations performed on a set of critical experiments designed to simulate high-density storage of reactor fuel pins. The purpose of these computations is to validate the Monte Carlo criticality code KENO V.a with the four cross-section libraries provided with the SCALE modular code system. The principal conclusion drawn from this study is the satisfactory performance of the SCALE cross-section libraries in the analysis of systems containing consolidated light-water reactor fuel. As observed in previous studies, the ENDF/B-IV-based libraries undercalculate the effective neutron multiplication factor (k_eff) by 1 to 2% k, depending on the degree of neutron moderation.

• 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); USDOE Office of Civilian Radioactive Waste Management
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6216182
• Report Number(s): CONF-871101-32; ON: DE87011672
• Country of Publication: United States
• Language: English

Related Subjects

050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
97 MATHEMATICS AND COMPUTING
Babcock & Wilcox Company
CALCULATION METHODS
COMPUTER CODES
CRITICALITY
CROSS SECTIONS
Evaluated Nuclear Data File (ENDF)
FUEL ELEMENTS
FUEL PINS
Fuel Pin
GAM-THERMOS Cross Sections
K CODES
KENO
MONTE CARLO METHOD
Monte Carlo Criticality Code
Neutron Moderations
Nuclear Criticality Safety Program (NCSP)
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
SCALE
SIMULATION
SPENT FUEL ELEMENTS
SPENT FUEL STORAGE
STORAGE
TESTING
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS