55 research outputs found
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Risk management activities at the DOE Class A reactor facilities
The probabilistic risk assessment (PRA) and risk management group of the Association for Excellence in Reactor Operation (AERO) develops risk management initiatives and standards to improve operation and increase safety of the DOE Class A reactor facilities. Principal risk management applications that have been implemented at each facility are reviewed. The status of a program to develop guidelines for risk management programs at reactor facilities is presented
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Frequency response testing at Experimental Breeder Reactor II using discrete-level periodic signals
The Experimental Breeder Reactor 2 (EBR-2) reactivity-to-power frequency-response function was measured with pseudo-random, discrete-level, periodic signals. The reactor power deviation was small with insignificant perturbation of normal operation and in-place irradiation experiments. Comparison of results with measured rod oscillator data and with theoretical predictions show good agreement. Moreover, measures of input signal quality (autocorrelation function and energy spectra) confirm the ability to enable this type of frequency response determination at EBR-2. Measurements were made with the pseudo-random binary sequence, quadratic residue binary sequence, pseudo-random ternary sequence, and the multifrequency binary sequence. 10 refs., 7 figs., 3 tabs
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SRS K-Reactor PRA LOCA analyses using best-estimate methods
The thermal-hydraulic system computer code RELAP5/MOD2.5 was used to investigate the response of the primary cooling system during loss-of-coolant accidents (LOCAs) at the Savannah River Site (SRS) K-Reactor. In contrast to the conservative safety analyses performed to support the restart of K-Reactor, the assumptions and boundary conditions used in the analyses described in this paper were carefully selected to reflect best-estimate values wherever possible. The results of the calculations indicate that, for a small break LOCA, one functional emergency cooling system pumping source combined with one operational injection path will maintain core cooling. For a large break LOCA, one additional injection path is needed. The incorporation of these results into the latest SRS K-Reactor Probabilistic Risk Assessment (PRA) contributed significantly to the reduction in severe core melt frequency over the previous version
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Dynamic analysis of the EBR-II plant with the DSNP-ND simulation package
Development and initial testing have been completed for a special version of the DSNP simulation language software package, DSNP-ND, which simulates EBR-II based on the models of the primary system components used in the NATDEMO program. Preliminary results are included for a comparison with an original NATDEMO prediction for the SHRT-45 transient. 7 refs
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Plutonium removal limit for the disposition of plutonium-bearing materials
Recent changes in world politics have resulted in the United States reducing its nuclear weapons and stopping plutonium production. Prior plutonium production, dismantling warheads, and decontamination and decommissioning some facilities have produced plutonium-bearing materials which must continue to be managed. As each lot of material is processed, the processor must decide whether to remove the plutonium before discarding the material or to discard it without plutonium removal. DOE has developed a new method of making this decision, called the Plutonium Removal Limit System (PRLS). The system is based on defining a plutonium concentration above which the cost of disposing of plutonium-bearing materials will be less if plutonium is recovered and below which the cost will be less if plutonium is discarded (following suitable waste treatment). This method minimizes the overall cost to DOE for disposing of the existing inventory of plutonium-bearing materials. The method was used to analyze the plutonium-discard limit for all categories of plutonium-bearing materials currently at each site. This analysis indicated the need to standardize the way sites make the remove-versus-discard decision. For this purpose, a set of departmental plutonium removal limits was developed. DOE expects to approve implementing this new method at all facilities handling plutonium-bearing material in FY 93
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Theoretical modeling of crevice and pitting corrosion processes in relation to corrosion of radioactive waste containers
A mathematical and numerical model for evaluation of crevice and pitting corrosion in radioactive waste containers is presented. The model considers mass transport, mass transfer at the metal/solution interface, and chemical speciation in the corrosion cavity. The model is compared against experimental data obtained in artificial crevices. Excellent agreement is found between modeled and experimental values. The importance of full consideration of complex ion formation in the aqueous solution is emphasized and illustrated. 10 refs., 5 figs
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Technologies for sorting, assaying, classifying, and certifying transuranic waste within the United States
At the Idaho National Engineering Laboratory (INEL), the Stored Waste Examination Pilot Plant (SWEPP) was developed to provide nondestructive examination and assay techniques for examining and certifying TRU wastes without opening the waste container. This technology was developed, primarily for stored TRU waste, to evaluate waste package compliance with Waste Disposal Acceptance Criteria and Transportation requirements prior to shipment. These techniques include real-time x-ray radiography, passive and active neutron assay, and ultrasonic container integrity examination. These techniques provide the necessary information to ensure safe transportation, handling, and disposal of the waste at the Waste Isolation Pilot Plant (WIPP). 1 ref., 3 figs
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The file of evaluated decay data in ENDF/B
One important application of nuclear decay data is the Evaluated Nuclear Data File/B, the base of evaluated nuclear data used in reactor research and technology activities within the US. This report discusses the decay data file
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Robotic applications at the Idaho National Engineering Laboratory
The Idaho National Engineering Laboratory (INEL) has several programs and projected programs that involve work in hazardous environments. Robotics/remote handling technology is being considered for an active role in these programs. The most appealing aspect of using robotics is in the area of personnel safety. Any task requiring an individual to enter a hazardous or potentially hazardous environment can benefit substantially from robotics by removing the operator from the environment and having him conduct the work remotely. Several INEL programs were evaluated based on their applications for robotics and the results and some conclusions are discussed in this paper. 1 fig
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Safety and environmental aspects of HYLIFE-II
The HYLIFE-II inertial confinement fusion reactor uses a Flibe spray for blast chamber protection and tritium breeding. HYLIFE-II is passively safe, having no large sources of energy available to disperse radioactive materials. The dominant activation product is {sup 18}F (half-life 110 minutes). Only a small fraction (< 10{sup {minus}5}) of the Flibe activation products would be mobilized. The offsite dose from a severe accident involving simultaneous failure of the blast chamber and containment building would be < 0.2 mSv (20 mrem), and N-stamp requirements could be avoided in the blast chamber and coolant systems. The required tritium removal efficiencies are quantified. 10 refs., 1 fig
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