Critical Experiments on 10% Enriched Uranyl Nitrate Solution Using an 80-cm-Diameter Cylindrical Core

Journal Article · Sat Mar 15 04:00:00 EST 2003 · Nuclear Technology

OSTI ID:20826832

Yamane, Yuichi; Miyoshi, Yoshinori; Watanabe, Shouichi; Yamamoto, Toshihiro ^[1]

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1. Japan Atomic Energy Research Institute (Japan)

The third series of the critical experiments on 10% enriched uranyl nitrate solution has been performed at the Static Experiment Critical Facility (STACY) of the Japan Atomic Energy Research Institute. Water-reflected and unreflected 80-cm-diam cylindrical cores were used to obtain the systematic data of critical solution height and differential reactivity for various uranium concentrations from 190 to 240 g/l. The numerically evaluated extrapolation length of neutron flux distribution was in good agreement with the experimental result. The effective neutron multiplication factor k{sub eff} for each core configuration and the effect of uncertainties on k{sub eff} were also numerically evaluated with both the detailed experimental configuration of critical cores and a benchmark model provided for the validation of nuclear calculation codes. The MCNP 4B was used for the evaluation calculations with JENDL-3.2 cross-section library, and the value of the k{sub eff} of the benchmark model was reproduced within the difference of 0.05% {delta}k{sub eff} for the water-reflector cores and 0.17% {delta}k{sub eff} for the unreflected cores.

• OSTI ID: 20826832
• Journal Information: Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 3 Vol. 141; ISSN 0029-5450; ISSN NUTYBB
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BENCHMARKS
CYLINDRICAL CONFIGURATION
EVALUATION
EXTRAPOLATION LENGTH
MULTIPLICATION FACTORS
NEUTRON FLUX
NEUTRONS
REACTIVITY
SOLUTIONS
STACY REACTOR
URANIUM
URANYL NITRATES
VALIDATION
WATER