國立虎尾科技大學 |

Experimental and Numerical Studies of Seismic Fluid-Structure-Interaction in Seismically-Isolated Advanced Nuclear Reactors.

Record Type:	Language materials, manuscript : Monograph/item
Title/Author:	Experimental and Numerical Studies of Seismic Fluid-Structure-Interaction in Seismically-Isolated Advanced Nuclear Reactors./
Author:	Mir, Faizan Ul Haq.
Description:	1 online resource (569 pages)
Notes:	Source: Dissertations Abstracts International, Volume: 84-12, Section: B.
Contained By:	Dissertations Abstracts International84-12B.
Subject:	Civil engineering. -
Online resource:	click for full text (PQDT)
ISBN:	9798379738693

Experimental and Numerical Studies of Seismic Fluid-Structure-Interaction in Seismically-Isolated Advanced Nuclear Reactors.
Mir, Faizan Ul Haq.

Experimental and Numerical Studies of Seismic Fluid-Structure-Interaction in Seismically-Isolated Advanced Nuclear Reactors. - 1 online resource (569 pages)

Source: Dissertations Abstracts International, Volume: 84-12, Section: B.

Thesis (Ph.D.)--State University of New York at Buffalo, 2023.

Includes bibliographical references

The seismic design of advanced reactors, particularly those that operate at near atmospheric pressure, will need to consider the interaction of the liquid coolant with enclosing or submerged components. The vessels in these reactors are thin-walled, with limited seismic capacity, and seismic isolation has been proposed to enable their construction. Design and risk calculations for seismically isolated advanced reactors will rely on the use of verified and validated numerical models that can accurately capture the interactions of the liquid coolant, the vessel, and the submerged structural/mechanical components (fluid-structure interaction: FSI), and the isolation-system responses. Validation of such numerical models and seismic isolation of advanced nuclear reactors are the two broad themes of this dissertation. The dissertation is organized into two parts, A and B. Part A describes physical experiments conducted to generate datasets for: 1) hydrodynamic responses in a conventionally supported fluid-filled vessel, 2) dynamic responses of components submerged in a conventionally supported vessel, and 3) hydrodynamic and isolation-system responses in a base-isolated, fluid-filled vessel. The experiments, executed on a six-degree-of-freedom earthquake simulator, used multi-directional seismic inputs with different intensities and frequency contents. The data generated in the physical experiments are used to validate numerical models for seismic FSI analysis of base-isolated or conventionally supported vessels and submerged components. The Arbitrary Lagrangian Eulerian (ALE) solver in LS-DYNA is used for the validation studies. Recommendations for validating numerical models for fluid-filled advanced reactors, using the data provided in part A, are provided. Part B describes experiments on a model of a seismically isolated fluoride-salt cooled high temperature reactor. The prototype reactor uses a fluoride salt as a coolant, graphite reflector blocks as a moderator, and circulating buoyant TRISO pebbles as the nuclear fuel. To characterize the behavior of reactor components under earthquake shaking, validate numerical models for seismic analysis, and develop recommendations for seismic design, a set of earthquake-simulator experiments on a scaled model of the reactor vessel and internals was executed on a six-degree-of-freedom earthquake simulator. The model was seismically isolated at its base using two types of spherical sliding bearings. The scaled model involved representations of prototype reactor vessel, core barrel, reflector blocks, coolant, and spherical fuel pebbles. The material and geometric properties of different test components were selected based on a dynamic similitude scaling analysis and an approximate length scale of 2.5. Three recorded earthquake motions and one synthetically generated motion, all triplets, were used as inputs for testing. The recorded earthquake motions were time scaled for consistency with the chosen length scale of the model. Instrumentation on the test specimen was focused on recording dynamic responses of the outer vessel, core barrel, and reflector-block assembly, hydrodynamic responses (sloshing and hydrodynamic pressure) of the liquid coolant, pebble consolidation under earthquake shaking, and the behavior of the representative isolation systems. Test results and numerical studies, building on the data generated in the tests and leading to recommendations for analysis and modelling, are presented in part B.

Electronic reproduction.
Ann Arbor, Mich. :
ProQuest,
2024

Mode of access: World Wide Web

ISBN: 9798379738693Subjects--Topical Terms:

561339
Civil engineering.
Subjects--Index Terms:

Advanced reactorsIndex Terms--Genre/Form:

554714
Electronic books.

Experimental and Numerical Studies of Seismic Fluid-Structure-Interaction in Seismically-Isolated Advanced Nuclear Reactors.
LDR:05019ntm a22004097 4500 001 1141730
005 20240414211458.5
006 m o d
007 cr mn ---uuuuu
008 250605s2023 xx obm 000 0 eng d
020 $a 9798379738693
035 $a (MiAaPQ)AAI30484948
035 $a AAI30484948
040 $a MiAaPQ $b eng $c MiAaPQ $d NTU
100 1 $a Mir, Faizan Ul Haq. $3 1465682
245 1 0 $a Experimental and Numerical Studies of Seismic Fluid-Structure-Interaction in Seismically-Isolated Advanced Nuclear Reactors.
264 0 $c 2023
300 $a 1 online resource (569 pages)
336 $a text $b txt $2 rdacontent
337 $a computer $b c $2 rdamedia
338 $a online resource $b cr $2 rdacarrier
500 $a Source: Dissertations Abstracts International, Volume: 84-12, Section: B.
500 $a Advisor: Whittaker, Andrew.
502 $a Thesis (Ph.D.)--State University of New York at Buffalo, 2023.
504 $a Includes bibliographical references
520 $a The seismic design of advanced reactors, particularly those that operate at near atmospheric pressure, will need to consider the interaction of the liquid coolant with enclosing or submerged components. The vessels in these reactors are thin-walled, with limited seismic capacity, and seismic isolation has been proposed to enable their construction. Design and risk calculations for seismically isolated advanced reactors will rely on the use of verified and validated numerical models that can accurately capture the interactions of the liquid coolant, the vessel, and the submerged structural/mechanical components (fluid-structure interaction: FSI), and the isolation-system responses. Validation of such numerical models and seismic isolation of advanced nuclear reactors are the two broad themes of this dissertation. The dissertation is organized into two parts, A and B. Part A describes physical experiments conducted to generate datasets for: 1) hydrodynamic responses in a conventionally supported fluid-filled vessel, 2) dynamic responses of components submerged in a conventionally supported vessel, and 3) hydrodynamic and isolation-system responses in a base-isolated, fluid-filled vessel. The experiments, executed on a six-degree-of-freedom earthquake simulator, used multi-directional seismic inputs with different intensities and frequency contents. The data generated in the physical experiments are used to validate numerical models for seismic FSI analysis of base-isolated or conventionally supported vessels and submerged components. The Arbitrary Lagrangian Eulerian (ALE) solver in LS-DYNA is used for the validation studies. Recommendations for validating numerical models for fluid-filled advanced reactors, using the data provided in part A, are provided. Part B describes experiments on a model of a seismically isolated fluoride-salt cooled high temperature reactor. The prototype reactor uses a fluoride salt as a coolant, graphite reflector blocks as a moderator, and circulating buoyant TRISO pebbles as the nuclear fuel. To characterize the behavior of reactor components under earthquake shaking, validate numerical models for seismic analysis, and develop recommendations for seismic design, a set of earthquake-simulator experiments on a scaled model of the reactor vessel and internals was executed on a six-degree-of-freedom earthquake simulator. The model was seismically isolated at its base using two types of spherical sliding bearings. The scaled model involved representations of prototype reactor vessel, core barrel, reflector blocks, coolant, and spherical fuel pebbles. The material and geometric properties of different test components were selected based on a dynamic similitude scaling analysis and an approximate length scale of 2.5. Three recorded earthquake motions and one synthetically generated motion, all triplets, were used as inputs for testing. The recorded earthquake motions were time scaled for consistency with the chosen length scale of the model. Instrumentation on the test specimen was focused on recording dynamic responses of the outer vessel, core barrel, and reflector-block assembly, hydrodynamic responses (sloshing and hydrodynamic pressure) of the liquid coolant, pebble consolidation under earthquake shaking, and the behavior of the representative isolation systems. Test results and numerical studies, building on the data generated in the tests and leading to recommendations for analysis and modelling, are presented in part B.
533 $a Electronic reproduction. $b Ann Arbor, Mich. : $c ProQuest, $d 2024
538 $a Mode of access: World Wide Web
650 4 $a Civil engineering. $3 561339
650 4 $a Geophysics. $3 686174
650 4 $a Architectural engineering. $3 1180400
653 $a Advanced reactors
653 $a Earthquake-simulator studies
653 $a Fluid-structure interaction
653 $a Numerical modelling
653 $a Seismic isolation
653 $a Submerged components
655 7 $a Electronic books. $2 local $3 554714
690 $a 0543
690 $a 0462
690 $a 0373
710 2 $a ProQuest Information and Learning Co. $3 1178819
710 2 $a State University of New York at Buffalo. $b Civil, Structural and Environmental Engineering. $3 1465683
773 0 $t Dissertations Abstracts International $g 84-12B.
856 4 0 $u http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=30484948 $z click for full text (PQDT)