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You searched for subject:(holtec). Showing records 1 – 3 of 3 total matches.

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Penn State University

1. Borza, Gregory Michael. Local Search Algorithm for Lattice Enrichment Optimization with Heuristics.

Degree: 2015, Penn State University

The objective of this study was to develop a lattice optimization tool to assist the loading pattern optimization of the HOLTEC SMR-160. Due to the use of cruciform control blades in the HOLTEC SMR-160 assembly design for controlling reactivity, a non-uniform pin enrichment distribution must be implemented. A non-uniform pin enrichment distribution helps mitigate the heterogeneity in the moderator distribution, allowing the lattice to have a flatter pin power shape. The optimization of the enrichment distribution within a lattice is a tedious yet important task to reduce high pin peak powers in full core simulations. The Standard Lattice Optimization Tool with Heuristics (SLOTH) was developed to automate the lattice enrichment optimization process while still allowing the user to have full control over the desired properties of the lattice (e.g. lattice average enrichment and burnable absorber distribution). It utilizes a local search algorithm in which the enrichment is incremented to minimize the pin peak power. Sensitivity studies indicate that the number of pins incremented at each iteration can be increased to five to ten pins without negatively impacting results. This allows SLOTH to optimize a lattice in approximately 90-150 minutes. Time is a key component in order for SLOTH to be an effective tool to assist in LP optimization. A heuristic biasing feature was included in SLOTH which allows the user to control the location of the pin peak power. This feature can be effective at gaining margin to thermal-hydraulic limits in instances where certain geometrical locations within the lattice are more likely to violate thermal-hydraulic limits than others. This feature was shown to be more effective in lattices with burnable absorbers, reducing pin peak power is specified locations by as much as 12.4% (using a 10% bias), compared to lattices without burnable absorbers. Advisors/Committee Members: Kostadin Nikolov Ivanov, Thesis Advisor/Co-Advisor.

Subjects/Keywords: Nuclear; Lattice; Optimization; Local Search; Enrichment; Holtec; SMR

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APA (6th Edition):

Borza, G. M. (2015). Local Search Algorithm for Lattice Enrichment Optimization with Heuristics. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/27472

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Borza, Gregory Michael. “Local Search Algorithm for Lattice Enrichment Optimization with Heuristics.” 2015. Thesis, Penn State University. Accessed February 24, 2021. https://submit-etda.libraries.psu.edu/catalog/27472.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Borza, Gregory Michael. “Local Search Algorithm for Lattice Enrichment Optimization with Heuristics.” 2015. Web. 24 Feb 2021.

Vancouver:

Borza GM. Local Search Algorithm for Lattice Enrichment Optimization with Heuristics. [Internet] [Thesis]. Penn State University; 2015. [cited 2021 Feb 24]. Available from: https://submit-etda.libraries.psu.edu/catalog/27472.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Borza GM. Local Search Algorithm for Lattice Enrichment Optimization with Heuristics. [Thesis]. Penn State University; 2015. Available from: https://submit-etda.libraries.psu.edu/catalog/27472

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


University of South Carolina

2. Priest, C. Ryan. Dosimetry, Activation, and Robotic Instrumentation Damage Modeling of the Holtec HI-STORM 100 Spent Nuclear Fuel System.

Degree: MS, Nuclear Engineering, 2016, University of South Carolina

The Holtec HI-STORM 100 spent fuel storage system is an intermediate storage mechanism for SNF assemblies. Long term licensing and storage requires consideration of material degradation of the stainless steel multi-purpose canister holding the spent fuel. This material degradation is predicted to take the form of environmentally assisted cracking on weld interfaces of the stainless steel cylinder. Several of these spent fuel storage arrays are located in coastal environments. These sites include both the Hope Creek and Diablo Canyon nuclear power stations. A multi-sensory robotic package is being designed for non-destructive assay of the cask annular environment. It will be necessarily exposed to radiation and high temperature. To inform the design of the robotic probe, radiation strength and spectra are modeled in SCALE 6.2 utilizing both ORIGEN-ARP and ORIGAMI for 0-D and 1-D characterization of spent fuel assembly radiation. Radiation transport is modeled within MCNP 6.1 for the case of both photons and neutrons in the annular environment and beyond. Radiation dose rate to operators and electronics was finely considered in regards to the insertion and operation of the probe within the cask annulus. This allows predictive quantification of radiation damage within components of the robotic probe. When planning robotic inspection procedure, accurate depiction of radiation source terms and transported radiation fields is a major concern. Predictions are made in relation to the shielded field of mixed species radiation for the purpose of operator and robotic interaction within the HI-STORM 100 system at different points in storage life. Advisors/Committee Members: Travis W. Knight.

Subjects/Keywords: Engineering; Nuclear Engineering; Dosimetry; Activation; Robotic Instrumentation; Damage Modeling; Holtec HI-STORM 100 Spent; Nuclear Fuel System

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Priest, C. R. (2016). Dosimetry, Activation, and Robotic Instrumentation Damage Modeling of the Holtec HI-STORM 100 Spent Nuclear Fuel System. (Masters Thesis). University of South Carolina. Retrieved from https://scholarcommons.sc.edu/etd/3832

Chicago Manual of Style (16th Edition):

Priest, C Ryan. “Dosimetry, Activation, and Robotic Instrumentation Damage Modeling of the Holtec HI-STORM 100 Spent Nuclear Fuel System.” 2016. Masters Thesis, University of South Carolina. Accessed February 24, 2021. https://scholarcommons.sc.edu/etd/3832.

MLA Handbook (7th Edition):

Priest, C Ryan. “Dosimetry, Activation, and Robotic Instrumentation Damage Modeling of the Holtec HI-STORM 100 Spent Nuclear Fuel System.” 2016. Web. 24 Feb 2021.

Vancouver:

Priest CR. Dosimetry, Activation, and Robotic Instrumentation Damage Modeling of the Holtec HI-STORM 100 Spent Nuclear Fuel System. [Internet] [Masters thesis]. University of South Carolina; 2016. [cited 2021 Feb 24]. Available from: https://scholarcommons.sc.edu/etd/3832.

Council of Science Editors:

Priest CR. Dosimetry, Activation, and Robotic Instrumentation Damage Modeling of the Holtec HI-STORM 100 Spent Nuclear Fuel System. [Masters Thesis]. University of South Carolina; 2016. Available from: https://scholarcommons.sc.edu/etd/3832


Penn State University

3. Kern, Ludwig August. FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK.

Degree: 2009, Penn State University

A FLUENT Computational Fluid Dynamics (CFD) model of a spent nuclear fuel dry storage cask was created to predict several critical design temperatures in order to aid in the design of a dry storage cask. Thermal tests were conducted to determine the ability of the FLUENT CFD code to accurately predict solid structure and fluid temperatures in simple and complex flow geometries. The thermal tests included natural convective flow in a single heated annular tube and realistic heating of a full-scale prototype dry storage cask using heating configurations which bounded the heat source distributions of all possible fuel loading patterns. The FLUENT CFD model of the prototype dry storage cask was successful in demonstrating reasonable accuracy (20% agreement) in predicting the majority of temperatures measured during the thermal tests. The model showed even better accuracy in predicting the hottest rod temperature, the hottest temperature within the cask, which is a critical design temperature, and conservatively bounded all rod temperatures if allowance is given for the measurement uncertainties in the experimental data. However, there was no validation during this set of thermal experiments of the FLUENT CFD model’s ability to accurately model heat transfer between adjacent rods in individual fuel assemblies, which will be necessary before the model is ready for use as part of the thermal design basis for spent nuclear fuel dry storage cask design. A general discussion of computational methods, modeling methodology, FLUENT and other CFD codes, spent nuclear fuel storage, the design of nuclear fuel dry storage casks, and the heat transfer mechanisms modeled for the dry storage cask is also included in addition to the information specific to the dry storage cask FLUENT CFD model and the model validation experiments conducted with the full-scale prototype cask. Advisors/Committee Members: Fan Bill B Cheung, Thesis Advisor/Co-Advisor, Fan Bill B Cheung, Thesis Advisor/Co-Advisor, John Michael Cimbala, Thesis Advisor/Co-Advisor.

Subjects/Keywords: Fluent; fluent modeling; cfd; cfd modeling; fluent model; cfd model; computational fluid dynamics; nuclear; nuclear engineering; dry storage; dry storage cask; spent fuel; spent nuclear fuel; nuclear fuel; rbmk; chernobyl; holtec; thermal; heat transfer; natural convection; convection; natural convective flow; annular; prototype; full-scale; validation; cfd code; navier-stokes; navier-stokes equation

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Kern, L. A. (2009). FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/9685

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Kern, Ludwig August. “FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK.” 2009. Thesis, Penn State University. Accessed February 24, 2021. https://submit-etda.libraries.psu.edu/catalog/9685.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Kern, Ludwig August. “FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK.” 2009. Web. 24 Feb 2021.

Vancouver:

Kern LA. FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK. [Internet] [Thesis]. Penn State University; 2009. [cited 2021 Feb 24]. Available from: https://submit-etda.libraries.psu.edu/catalog/9685.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Kern LA. FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK. [Thesis]. Penn State University; 2009. Available from: https://submit-etda.libraries.psu.edu/catalog/9685

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

.