Criticality Evaluation for the Storage of Converter Plates in Drums

Conference · Sat Jun 19 00:00:00 EDT 1993

OSTI ID:10129884

Hu, J. P. ^[1]; Rorer, D. C. ^[1]; Liu, H. B. ^[1]

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1. Brookhaven National Laboratory (BNL), Upton, NY (United States)

A criticality safety evaluation was performed to support the temporary storage of 20%-enriched uranium converter plates for future use in the Brookhaven Medical Research Reactor (BMRR). A total of twelve such plates each containing approximately one kilogram of the ²³⁵U will be stored in DOT-certified 6M-drums, which have the same dimensions as standard 55-gallon drums except that they are twice as high (178.5cm). Each drum contains a Celotex liner surrounding a central 12.7cm-dia steel pipe. The plates have a nominal size of 0.3cmxl0.5cm . l25.7cm and fit inside the steel pipe, which extends 130cm in the axial direction. Because the accommodation of twelve plates in one drum is physically possible and more economical, this option for plate storage would be recommended provided that the criticality safety limit is not exceeded. In this paper, the neutron multiplication K_eff in drums is calculated using the Monte Carlo Neutron and Photon Transport code (MCNP). For conservatism, several different configurations which could result.in the most reactive conditions for K_eff have been examined. As part of the effort to optimize the arrangement of plates in drums, a second group of the MCNP calculations is performed using twelve plates evenly contained within two drums placed immediately adjacent to each other model again simulates the most reactive conditions for K_eff estimations.

• Research Organization: Brookhaven National Laboratory (BNL), Upton, NY (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 10129884
• Report Number(s): BNL-49869; CONF-9306305-2; ON: DE94005453; TRN: 94:007323
• Resource Relation: Conference: 1994 American Nuclear Society (ANS) Annual Meeting , New Orleans, LA (United States), 19-23 Jun 1993; Other Information: PBD: [1993]
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
ENRICHED URANIUM
STORAGE
CRITICALITY
MATHEMATICAL MODELS
SAFETY
CONCENTRATION RATIO
Nuclear Criticality Safety Program (NCSP)
Enriched Uranium Converter Plates
Brookhaven Medical Research Reactor (BMRR)
Monte Carlo Neutron and Photon Transport code (MCNP)
K-Effective
420203
HANDLING EQUIPMENT AND PROCEDURES