S/sub n/ analysis of the TRX metal lattices with ENDF/B version III data

Conference · Sat Mar 01 00:00:00 EDT 1975

OSTI ID:4110434

Wheeler, F J; Pearlstein, S ^[1]

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1. ed.

Two critical assemblies, designated as thermal-reactor benchmarks TRX-1 and TRX-2 for ENDF/B data testing, were analyzed using the one-dimensional S/sub n/-theory code SCAMP. The two assemblies were simple lattices of aluminum-clad, uranium-metal fuel rods in triangular arrays with D$sub 2$O as moderator and reflector. The fuel was low-enriched (1.3 percent $sup 235$U), 0.387-inch in diameter and had an active height of 48 inches. The volume ratio of water to uranium was 2.35 for the TRX-1 lattice and 4.02 for TRX-2. Full-core S/sub n/ calculations based on Version III data were performed for these assemblies and the results obtained were compared with the measured values of the multiplication factors, the ratio of epithermal-to-thermal neutron capture in $sup 238$U, the ratio of epithermal-to-thermal fission in $sup 235$U, the ratio of $sup 238$U fission to $sup 235$U fission, and the ratio of capture in $sup 238$U to fission in $sup 235$U. Reaction rates were obtained from a central region of the full- core problems. Multigroup cross sections for the reactor calculation were obtained from S/sub n/ cell calculations with resonance self-shielding calculated using the RABBLE treatment. The results of the analyses are generally consistent with results obtained by other investigators. (auth)

• Research Organization: Aerojet Nuclear Co., Idaho Falls, ID; Brookhaven National Lab., Upton, N.Y. (USA)
• NSA Number: NSA-33-016358
• OSTI ID: 4110434
• Report Number(s): BNL-NCS-50451; CONF-750323-
• Resource Relation: Conference: Proceedings of 238U resonance capture, Upton, New York, USA, 18 Mar 1975; Other Information: Orig. Receipt Date: 30-JUN-76; Related Information: Seminar on the $sup 238$U resonance capture
• Country of Publication: United States
• Language: English

Related Subjects

N77600* -Reactors-Research
Test
Experimental
Zero-power & Training Reactors
& Subcritical Assemblies
220600* -Nuclear Reactor Technology-Research
Test & Experimental Reactors
*ZERO POWER REACTORS- REACTOR LATTICE PARAMETERS
CARLSON METHOD
CROSS SECTIONS
NEUTRON REACTIONS
NUCLEAR DATA COLLECTIONS
S CODES
URANIUM 235
URANIUM 238