Twenty-six male and female collegiate and semiprofessional/professional soccer players (age = 20.4 ± 2.0 years; height = 172.1 ± 8.2 cm; weight = 70.7 ± 10.8 kg) participated in this study to determine the reliability and validity of a field anaerobic shuttle test (FAST) and the Cunningham and Faulkner (1969) treadmill anaerobic speed test (AST). The relationship between the AST and FAST was also investigated. Intraclass reliability coefficients were acceptable for the FAST (.96) and AST (.97) with no significant difference between the means at T 1 and T 2 (FAST = 56.0 vs. 55.8 sec; AST = 41.9 vs. 41.4 sec). Poor reliability for the Wingate Anaerobic Test (WAT), .83 (W), .70 (W · kg -1 ), necessitated correcting the validity coefficients for attenuation, FAST vs. WAT = -.89 (W) and -.71 (W · kg -1 ); AST vs. WAT = .82 (W) and .74 (W · kg -1 ). These coefficients provide preliminary evidence that the construct being measured is anaerobic work capacity. The results (FAST vs. AST = -.85) indicate that FAST and AST appear to be measuring the same construct. Further research is needed to substantiate the validity of AST and FAST scores as measures of anaerobic work capacity of collegiate and professional soccer players.

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EXECUTIVE SUMMARYThis report describes the first in a series of studies in support of the US Department of Energy's (DOE) Consolidated Fuel Reprocessing Program. These studies develop and evaluate designs of advanced materials measurement and accounting systems (MMASs) for various nuclear spent-fuel reprocessing alternatives. This report examines safeguards design concepts for the feed preparation and chemical separations processes of the Hot Experimental Facility (HEF), a conceptual fast breeder reactor spent-fuel reprocessing facility. We propose an MMAS and use optimization techniques to calculate instrument measurement uncertainties that meet four different accounting performance goals while minimizing the total development cost of instrument systems. We identify measurement uncertainty components that dominate the materials balance variance and instruments that require development to meet given performance goals.Conceptual design efforts for MMASs are a major portion of an integrated safeguards systems study program that is implemented by the Safeguards Systems Group (Q-4) of the Los Alamos National Laboratory, at the direction of the US DOE/Office of Safeguards and Security. These designs invoke technology that has been demonstrated or can be projected within the construction schedules of future nuclear fuel-cycie facilities. The studies define systems concepts, develop methods for evaluating safeguards systems and the data they produce, and should stimulate further development of facilities, processes, systems, and instrumentation needed for improving nuclear materials accounting, thus providing more effective safeguards.Previous Los Alamos National Laboratory studies in the safeguards conceptual design series address the materials management requirements for mixed-oxide fuel refabrication facilities (LA-6536), domestic and foreign spent-fuel reprocessing plants (LA-6881 and LA-8042), plutonium nitrate conversion (LA-7011) and coconversion facilities (LA-7521 and LA-7746-MS), spent-fuel storage ponds (LA-7730-MS), thorium-uranium fuel-cycle facilities (LA-7372 and LA-7411-MS), large fast-critical reactors (LA-7315), and nuclear waste repositories (LA-8049-MS). In general, these studies calculate the accounting systems performance by proposing a measurement system based on current technology or its reasonable extrapolations. The measurement uncertainties for each proposed instrument are then combined and propagated to obtain an overall materials loss-detection sensitivity.This study reverses the approach. We select specific accounting performance goals for the HEF and use optimization techniques to calculate measurement uncertainties required to meet these goals while minimizing the total development cost of the instrument system.The design for Oak Ridge National Laboratory's HEF incorporates a modified Purex process that allows coprocessing uranium and plutonium. The flow sheet is based on reprocessing 0.5 tonne/day of breeder reactor fuel having (1) a maximum burnup of 150 000 megawatt-days per tonne, (2)...

A model ol an operating conversion and purification piucess lor the production of reactor-grade Plutonium uioxiue was developed as the first component in the design and evaluation ot a nuclear materials measurement and accountability system. The model accurately simulates process operation and can be used to identify process problems and to predict t:ie effect of process modifications. 1.