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S Sitaraman

Bio: S Sitaraman is an academic researcher from Lawrence Livermore National Laboratory. The author has contributed to research in topics: Spent fuel pool & Spent nuclear fuel. The author has an hindex of 5, co-authored 16 publications receiving 59 citations.

Papers
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Proceedings ArticleDOI
20 Apr 2015
TL;DR: In this paper, the authors presented the first successful field testing using the integrated PDET system and actual spent fuel assemblies performed in a commercial spent fuel storage site, known as Central Interim Spent fuel storage facility (CLAB) in Sweden.
Abstract: The need for the development of a credible method and instrument for partial defect verification of spent fuel has been emphasized over a few decades in the safeguards communities as the diverted spent fuel pins can be the source of nuclear terrorism or devices. The need is increasingly more important and even urgent as many countries have started to transfer spent fuel to so called "difficult-to-access" areas such as dry storage casks, reprocessing or geological repositories. Partial defect verification is required by IAEA before spent fuel is placed into "difficult-to-access" areas. Earlier, Lawrence Livermore National Laboratory (LLNL) has reported the successful development of a new, credible partial defect verification method for pressurized water reactor (PWR) spent fuel assemblies without use of operator data, and further reported the validation experiments using commercial spent fuel assemblies with some missing fuel pins. The method was found to be robust as the method is relatively invariant to the characteristic variations of spent fuel assemblies such as initial fuel enrichment, cooling time, and burn-up. Since then, the PDET system has been designed and prototyped for 17×17 PWR spent fuel assemblies, complete with data acquisition software and acquisition electronics. In this paper, a summary description of the PDET development followed by results of the first successful field testing using the integrated PDET system and actual spent fuel assemblies performed in a commercial spent fuel storage site, known as Central Interim Spent fuel Storage Facility (CLAB) in Sweden will be presented. In addition to partial defect detection initial studies have determined that the tool can be used to verify the operator declared average burnup of the assembly as well as intra-assembly bunrup levels.

9 citations

Journal ArticleDOI
TL;DR: In this article, a novel methodology to detect diversion of spent fuel from pressurized water reactors (PWRs) has been developed in order to address a long unsolved safeguards verification problem for an internatio...
Abstract: A novel methodology to detect diversion of spent fuel from pressurized water reactors (PWRs) has been developed in order to address a long unsolved safeguards verification problem for an internatio...

8 citations

Journal ArticleDOI
TL;DR: The National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory (LLNL) is scheduled to be operational within a year and the 192 laser beam facility will be operational and the expe...
Abstract: Commissioning shots have commenced at the National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory. Within a year, the 192 laser beam facility will be operational and the expe...

7 citations

Patent
17 Nov 2009
TL;DR: In this paper, the authors detect diversion of spent fuel from PWRs by determining possible diversion including the steps of providing a detector cluster containing gamma ray and neutron detectors, inserting the detectors into the spent fuel assembly through the guide tube holes and processing the gamma and neutron radiation responses at the locations by normalizing them to the maximum value among each set of responses.
Abstract: Detecting diversion of spent fuel from Pressurized Water Reactors (PWR) by determining possible diversion including the steps of providing a detector cluster containing gamma ray and neutron detectors, inserting the detector cluster containing the gamma ray and neutron detectors into the spent fuel assembly through the guide tube holes in the spent fuel assembly, measuring gamma ray and neutron radiation responses of the gamma ray and neutron detectors in the guide tube holes, processing the gamma ray and neutron radiation responses at the guide tube locations by normalizing them to the maximum value among each set of responses and taking the ratio of the gamma ray and neutron responses at the guide tube locations and normalizing the ratios to the maximum value among them and producing three signatures, gamma, neutron, and gamma-neutron ratio, based on these normalized values, and producing an output that consists of these signatures that can indicate possible diversion of the pins from the spent fuel assembly.

5 citations


Cited by
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Journal ArticleDOI
TL;DR: In this paper, a review on the influences of various factors on the moisture susceptibility of WMA mixtures is presented, where the influence of materials and technologies are illustrated, including aggregate, asphalt, compacting temperature and other warm mix technologies.

113 citations

Patent
Oh Kwang Seok1
30 Nov 2017
TL;DR: In this paper, the authors propose a semiconductor memory consisting of a substrate and a stepped structure including first interlayer dielectric layers and conductive layers which are alternately stacked over the substrate.
Abstract: Provided is an electronic device including a semiconductor memory. The semiconductor memory may include: a substrate; and a stepped structure including first interlayer dielectric layers and conductive layers which are alternately stacked over the substrate, wherein ends of the conductive layers are exposed along the profile of the stepped structure, and the stepped structure further includes a barrier layer formed on a sidewall of the conductive layer.

23 citations

Journal ArticleDOI
TL;DR: In this work, a new MCNP model of the Tokamak Complex is conceived to be computationally stable while capturing a conservative representation of the baseline, and a novel approach to model the plasma source, called a mosaic source, allows an unprecedented degree of realism and accuracy in terms of capturing the port specificities.
Abstract: The ITER Tokamak Complex is the civil structure that will host the ITER Tokamak and the largest part of the associated systems. The dimensions are 120 m × 80 m × 60 m, built mostly of concrete, with over one thousand penetrations. During ITER operation, a radiation field will spread throughout the complex from diverse radiation sources. It must be characterized to check the compliance with the limits for electronics allocation and human intervention. However, the production of radiation maps in the ITER Tokamak Complex is a task of paramount sophistication due to challenges to adequately model in MCNP the radiation sources involved. In this work, two important methodological upgrades are presented. First, a new MCNP model of the Tokamak Complex, conceived to be computationally stable while capturing a conservative representation of the baseline. Second, a novel approach to model the plasma source, called a mosaic source, allows an unprecedented degree of realism and accuracy in terms of capturing the port specificities. Both represent a step change in the capacity to produce ITER radiation maps with increased reliability, augmenting previous versions. Examples of partial radiation maps are provided considering both methodological upgrades.

18 citations