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[en] This document provides a general narrative description of the AFC-2A and 2B fuel fabrication processes for the AFC 2A and AFC 2B fuel irradiation experiments fabricated at the Idaho National Laboratory's Materials and Fuels Complex (MFC) for irradiation in the Advanced Test Reactor (ATR)
[en] The Nuclear Science User Facilities (NSUF), established in 2007 as the Advanced Test Reactor (ATR) National Scientific User Facility is chartered to provide cost-free access to unique and important research and development capabilities and infrastructure to nuclear energy-focused researchers. Users can apply for access to any of the NSUF INL or partner facilities using the same process, either through the annual Office of Nuclear Energy Consolidated Innovative Nuclear Research funding announcement or the NSUF Rapid Turnaround Experiment (RTE) opportunities, offered three times each year. The NSUF has several research and test reactors available as well as ion beamlines and x-ray light sources for experimental use in support of the R&D objectives of the DOE Office of Nuclear Energy. This presentation reviews the current capabilities, needs, awarded irradiation experiments and potential use in FY 2018.
[en] This study investigates autothermal reforming of fuel cell-grade methanol as a method for producing hydrogen for transportation applications. A previous study on the effects of oxygen-to-carbon ratio on ATR reactor performance showed that the optimum of O2/CH3OH=0.30 found in the experimental tests is 30% higher than the theoretical optimum of 0.23. In this study, the influence of catalyst bed length is investigated to give insight into the reaction progression through the catalyst bed in methanol autothermal reformation. The effect of reaction progression through the catalyst bed is experimentally investigated in relation to reactor output parameters of fuel conversion, temperature profile, and reactor efficiency. The results from this study serve as a baseline for future research of autothermal reforming of hydrocarbon fuels as a method for producing hydrogen
[en] A prototype of a transient reactivity meter (TRM) has been constructed and successfully tested at the ATR critical facility. This TRM is a combination hard-wired/programmable analog computer that performs a closed-loop inverse solution of the space-independent reactor kinetics differential equations. It has several features, compared with those of other reactivity-measuring devices, that provide distinct advantages in performing reactivity measurements: (1) It is a closed-loop solution (which is inherently stable) wherein the solution rho is ''forced'' at the output of a high-gain network. (2) The solution for rho is performed entirely within the negative feedback loop, thus minimizing the required number of calculational stages and components. (3) It will recover when reset (to the initial-condition mode) during maneuvering (slow) positive transients, thus accommodating input range-switching during such transients. (4) It is programmable to the extent that delay-group parameters, input and output ranges, and tau0 (or l/β/sub eff/) can be readily changed and/or readjusted to provide for its use with different reactors or to compensate for aging of electrical components. (5) It has a built-in test function, which provides for rapid checkout in the field
[en] The flat plate nuclear fuel used in the Advanced Test Reactor (ATR) has several attributes which are best examined by radiography. These are fuel core dimensions and location, homogeneity of the uranium aluminide alloy that composes the core, and the location and sizing of fuel particles in the fuel free edge borders of the plates. The most economiccal approach is to inspect for all three attributes from a single radiograph which requires accommodation of a large contrast range. Currently radiography is conducted using Kodak type M double emulsion film which provides a high quality image for evaluation. A promising alternative to film exists however in paper radiography. The two media are very similar except that paper uses a single emulsion which is deposited on an opaque diffuse reflecting surface. This requires that the image be viewed with reflected rather than transmitted light. This type of physical structure results in lower materials and processing costs. For example, Kodak Industrex 600 paper is approximately 50% the cost of type M film. In addition the image can be developed and viewed (although not fixed) in as little as 10 seconds. The results of test to ascertain the suitability of paper radiography for these purposes are described. Whole there was some degradation of the image with the use of paper, the paper was judged suitable for identification of edge border location, homogeneity, and floking
[en] The Advanced Test Reactor (ATR) Complex, operated by Battelle Energy Alliance, LLC, at the Idaho National Laboratory (INL) conducted an evaluated drill on October 6, 2015, to allow the ATR Complex emergency response organization (ERO) to demonstrate the ability to respond to and mitigate an emergency by implementing the requirements of DOE O 151.1C, ''Comprehensive Emergency Management System.''
[en] This report describes activities of the ATR NSUF from FY-2008 through FY-2009 and includes information on partner facilities, calls for proposals, users week and education programs. The report also contains project information on university research projects that were awarded by ATR NSUF in the fiscal years 2008 and 2009. This research is university-proposed researcher under a user facility agreement. All intellectual property from these experiments belongs to the university per the user agreement.
[en] The use of performance indicators at the Advanced Test Reactor was considerably expanded in 1988. Where seven indicators had before been formally reported, the number has since been increased to 30. While some of the indicators are similar to those used by the commercial nuclear power industry, many are unique to the requirements of the Advanced Test Reactor. Some indicators may also have applicability to other test reactors. The purpose of this paper is to present the development of performance indicators and describe in detail the manner in which a few of the more unique or important indicators are reported. The intended result is a measure of plant performance with improved safety and operation