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iLAMP: Neutron Absorber Material Monitoring for Spent Fuel Pools
The spent fuel pool at TVA’s Watts Bar nuclear power plant near Spring City, Tenn. (Photo: TVA)
Neutron absorber materials are used by nuclear power plants to maintain criticality safety margins in their spent nuclear fuel pools. These materials are typically in the form of fixed panels of a neutron-absorbing composite material that is placed within the fuel pools. (A comprehensive review of such materials used in wet storage pools and dry storage has been provided by the Electric Power Research Institute (EPRI) [1]).
With increasing plant life, there is a need to maintain or establish a monitoring program for neutron absorber materials—if one is not already in place—as part of aging management plans for reactor spent fuel pools.
Such monitoring programs are necessary to verify that the neutron absorbers continue to provide the criticality safety margins relied upon in the criticality analyses of a reactor’s spent fuel pool. To do this, the monitoring program must be capable of identifying any changes to the material and quantifying those changes. It should be noted that not all the changes (for example minor pitting and blistering of the absorber material) will result in statistically or operationally significant impact on the criticality safety margins.
For monitoring neutron absorber materials in spent fuel pools, until recently, two alternatives existed—coupon testing and in situ measurements. A third option, called industry-wide learning aging management program (i-LAMP), was proposed by EPRI and is currently in the final stages of the regulatory review. The following sections describe these monitoring approaches.
N. C. Logan, B. A. Grierson, S. R. Haskey, S. P. Smith, O. Meneghini, D. Eldon
Fusion Science and Technology | Volume 74 | Number 1 | July-August 2018 | Pages 125-134
Technical Paper | doi.org/10.1080/15361055.2017.1386943
Articles are hosted by Taylor and Francis Online.
One Modeling Framework for Integrated Tasks (OMFIT) has been used to develop a consistent tool for interfacing with, mapping, visualizing, and fitting tokamak profile measurements. OMFIT is used to integrate the many diverse diagnostics on multiple tokamak devices into a regular data structure, consistently applying spatial and temporal treatments to each channel of data. Tokamak data are fundamentally time dependent and are treated so from the start, with front-loaded and logic-based manipulations such as filtering based on the identification of edge-localized modes (ELMs) that commonly scatter data. Fitting is general in its approach, and tailorable in its application in order to address physics constraints and handle the multiple spatial and temporal scales involved. Although community standard one-dimensional fitting is supported, including scale length–fitting and fitting polynomial-exponential blends to capture the H-mode pedestal, OMFITprofiles includes two-dimensional (2-D) fitting using bivariate splines or radial basis functions. These 2-D fits produce regular evolutions in time, removing jitter that has historically been smoothed ad hoc in transport applications. Profiles interface directly with a wide variety of models within the OMFIT framework, providing the inputs for TRANSP, kinetic-EFIT 2-D equilibrium, and GPEC three-dimensional equilibrium calculations. The OMFITprofiles tool’s rapid and comprehensive analysis of dynamic plasma profiles thus provides the critical link between raw tokamak data and simulations necessary for physics understanding.