Subcriticality of two uranyl nitrate flat cylindrical tanks spaced in air by [sup 252]Cf-source-driven noise analysis

Journal Article · Wed Sep 01 00:00:00 EDT 1993 · Nuclear Technology; (United States)

DOI:https://doi.org/10.13182/NT93-3· OSTI ID:5982020

Mihalczo, J T; Blakeman, E D; Pare, V K; Valentine, T E; Auslander, D J ^[1]

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1. Oak Ridge National Lab., TN (United States)

The subcritical neutron multiplication factors k for two parallel, axially separated, flat cylindrical tanks separated up to 57.91cm in air and containing enriched uranyl (93.1 wt% [sup 235]U) nitrate solution (71.6-cm-i.d. tanks, 8.91-cm solution thickness, 1.555 g/cm[sup 3] solution density, and 404g U/l uranium density) were measured by the [sup 252]Cf-source-driven noise analysis method with measured k values varying from 0.99 to 0.80. These measurements were performed at the Los Alamos National Laboratory (LANL) Critical Experiments Facility in 1989 and were part of the program of Westinghouse Idaho Nuclear Company (WINCO) to benchmark calculations for the design of the new storage system at Idaho National Engineering Laboratory. Initial subcriticality measurements by the source-jerk method at LANL had indicated that at a calculated neutron multiplication factor k = 0.95, the measured k was 0.975. This discrepancy was of concern to WINCO because the new storage facility was being designed with a k limit of 0.95, and thus, half of the criticality safety margin of the storage design was equal to the discrepancy between early measurements and calculations. The [sup 252]Cf-source-driven noise analysis measurements confirmed the validity of the calculational methods. In addition to providing the neutron multiplication factor from point-kinetics interpretation of the data, these measurements also provided the auto-power and cross-power spectral densities as a function of frequency, which can be calculated directly with recently developed Monte Carlo methods and thus could also be used to validate calculational methods and cross-section sets.

• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5982020
• Journal Information: Nuclear Technology; (United States), Vol. 103:3; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
IDAHO NATIONAL ENGINEERING LABORATORY
STORAGE FACILITIES
DESIGN
URANYL NITRATES
SUBCRITICALITY
BENCHMARKS
MULTIPLICATION FACTORS
POSITIONING
SAFETY
TANKS
ZERO POWER REACTORS
ACTINIDE COMPOUNDS
CONTAINERS
EXPERIMENTAL REACTORS
NATIONAL ORGANIZATIONS
NITRATES
NITROGEN COMPOUNDS
OXYGEN COMPOUNDS
REACTORS
RESEARCH AND TEST REACTORS
URANIUM COMPOUNDS
URANYL COMPOUNDS
US DOE
US ERDA
US ORGANIZATIONS
420203* - Engineering- Handling Equipment & Procedures
050900 - Nuclear Fuels- Transport
Handling
& Storage