KENO V. a Validation of Fuel Pin Experiments

Conference · Sun Nov 15 00:00:00 EST 1987 · Transactions of the American Nuclear Society

OSTI ID:6944333

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

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

The results of computations performed on a set of critical experiments designed to simulate high-density storage of reactor fuel pins are described. 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. A series of 21 critical experiments, performed by the Babcock and Wilcox Company to simulate close-packed fuel pin storage, was modeled. The CSAS4 control module within SCALE was used to calculate the effective neutron multiplication factor (k/sub eff/) via the KENO V.a criticality code. The experiments consisted of 5 x 5 arrays of fuel pin modules each approx. 19-cm square.

• 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)
• OSTI ID: 6944333
• Report Number(s): CONF-8711195-; CODEN: TANSA; TRN: 88-031828
• Journal Information: Transactions of the American Nuclear Society, Vol. 55; Conference: American Nuclear Society Winter Meeting, Los Angeles, CA (United States), 15 Nov 1987; ISSN 0003-018X
• Publisher: American Nuclear Society
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
97 MATHEMATICS AND COMPUTING
CRITICALITY
K CODES
FUEL PINS
STORAGE
C CODES
CROSS SECTIONS
MULTIPLICATION FACTORS
S CODES
SAFETY
COMPUTER CODES
FUEL ELEMENTS
REACTOR COMPONENTS
Nuclear Criticality Safety Program (NCSP)
Results
Critical Experiments
Reactor Fuel Pins High-Density Storage
050900* - Nuclear Fuels- Transport
Handling
& Storage
420203 - Engineering- Handling Equipment & Procedures