Language:
English
繁體中文
Help
回圖書館首頁
手機版館藏查詢
Login
Back
Switch To:
Labeled
|
MARC Mode
|
ISBD
The Role of Seismic Isolation in the...
~
Lal, Kaivalya Mitesh,
Linked to FindBook
Google Book
Amazon
博客來
The Role of Seismic Isolation in the Deployment of Advanced Nuclear Reactors /
Record Type:
Electronic resources : Monograph/item
Title/Author:
The Role of Seismic Isolation in the Deployment of Advanced Nuclear Reactors // Kaivalya Mitesh Lal.
Author:
Lal, Kaivalya Mitesh,
Description:
1 electronic resource (658 pages)
Notes:
Source: Dissertations Abstracts International, Volume: 86-03, Section: B.
Contained By:
Dissertations Abstracts International86-03B.
Subject:
Engineering. -
Online resource:
https://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=31555997
ISBN:
9798384085782
The Role of Seismic Isolation in the Deployment of Advanced Nuclear Reactors /
Lal, Kaivalya Mitesh,
The Role of Seismic Isolation in the Deployment of Advanced Nuclear Reactors /
Kaivalya Mitesh Lal. - 1 electronic resource (658 pages)
Source: Dissertations Abstracts International, Volume: 86-03, Section: B.
Major impediments to the widespread deployment of new nuclear power plants (NPPs) are high overnight capital cost (OCC) and lengthy time for deployment. The seismic load case is a key driver of the capital cost and longer deployment times and thwarts deployment of standardized reactors as the near-surface geology and seismic hazard are never identical at any two sites. Seismic isolation is a proven, mature technology that offers a means to minimize the effects of earthquake shaking and can enable deployment advanced NPPs with substantially lower OCC and deployment duration. Exploring the role of seismic isolation to enable rapid deployment of new build NPPs is the broad theme of this dissertation, organized into two parts, A and B.The conventional implementation of seismic isolation involves isolating a reactor building at its base. An alternate approach, when building isolation is not practical, involves isolating equipment inside a reactor building. Mid-height seismic isolation of equipment is the focus of Part A of this dissertation: an application not studied previously and considered here to expand the range of options available to designers of safety-class equipment in advanced reactors. It describes proof-of-concept of experiments to investigate the efficacy of mid-height seismic isolation for a tall, slender cylindrical vessel, which could represent a reactor vessel, a steam generator, or a heat exchanger in an advanced nuclear power plant. The carbon steel test article was 20 ft tall with an outer diameter of 5 ft inches and a wall thickness of 1 inch. It was supported near its center of gravity (at its mid-height) on a stiff steel frame using three radial mounts. Three configurations of the vessel were tested: non-isolated, isolated using single Friction Pendulum (SFP) bearings, and isolated using triple Friction Pendulum (TFP) bearings. The vessel was subjected to three component ground motions using a 6 degrees-of-freedom earthquake simulator. The vessel was filled with water during testing to simulate in-service conditions. The test results demonstrated that mid-height seismic isolation enables a significant reduction in horizontal spectral accelerations in the vessel. Numerical models of the non-isolated and isolated vessel were developed, and it was demonstrated that the response of a mid-height isolated tall, slender vessel and its isolation system can be predicted using currently available analysis software. The benchmarked numerical models were used to quantify the benefits of mid-height isolation and demonstrate that the reductions in horizontal spectral accelerations are by-and-large independent of support structure stiffness. Base isolation, although viable, may not be a practical choice for tall, slender equipment because rocking of the vessel may lead to significant changes in axial load on the bearings and possibly axial tension (or uplift in the case of spherical sliding isolators). Mid-height isolation virtually eliminated the rocking response, and with it, the large changes in axial load. Analysis and design recommendations for isolation of equipment in nuclear facilities are also provided.Part B of this dissertation addresses soil-structure-interaction analysis of surface-mounted, seismically isolated advanced reactor buildings. The current rules and guidance for SSI analysis of NPPs are based on the legacy assumption that reactor buildings are both very heavy and stiff: the two key attributes needed for significant SSI on soil sites. Many of the advanced and micro reactors designs (hereafter grouped together as advanced reactors) are one or two orders of magnitude lighter and smaller than their gigawatt-scale predecessors. Reactor developers are considering seismic isolation as a design feature to reduce the impact of the seismic loads, adding flexibility at the reactor building base. The substantial reduction in both weight and stiffness leads to the hypothesis that SSI may have negligible influence on seismically isolated advanced reactors. In a first-of-a-kind study wherein reactor buildings and their safety-class equipment, the supporting soil domains, and nonlinear isolation systems are explicitly modeled and analyzed together, Part B of this dissertation determines whether this hypothesis is correct.An extensive set of response-history analyses was performed for combinations of 1) three fundamentally different advanced reactor buildings, 2) five horizontal isolation systems with a range of linear and bilinear isolator properties, 3) nine seismic inputs covering a range of frequencies and amplitudes of shaking, and 4) seven generic soil profiles that cover a range of sites across the U.S. and were a part of the Design Certification Documents that enabled the KEPCO APR1400 to be certified for use by the USNRC under the 10CFR Part 52 licensing framework, resulting in a total of 945 combinations. The analyses results demonstrated that SSI had negligible no meaningful effect on the in-structure acceleration response of the reactor buildings and the force-displacement behavior of their isolation systems. The peak horizontal displacements of the isolation systems and the peak horizontal accelerations at two locations in each reactor building were essentially identical with and without considering SSI. Using surface-free-field representations of ground shaking for design of surface- (and near-surface-) supported base-isolated advanced reactor buildings, without the need for SSI analysis, is the key recommendation of Part B.
English
ISBN: 9798384085782Subjects--Topical Terms:
586835
Engineering.
Subjects--Index Terms:
Advanced nuclear reactors
The Role of Seismic Isolation in the Deployment of Advanced Nuclear Reactors /
LDR
:07157nmm a22004573i 4500
001
2434169
005
20250912100607.5
006
m o d
007
cr|nu||||||||
008
261011s2024 miu||||||m |||||||eng d
020
$a
9798384085782
035
$a
(MiAaPQD)AAI31555997
035
$a
AAI31555997
040
$a
MiAaPQD
$b
eng
$c
MiAaPQD
$e
rda
100
1
$a
Lal, Kaivalya Mitesh,
$e
author.
$0
(orcid)0000-0001-7827-435X
$3
3824059
245
1 0
$a
The Role of Seismic Isolation in the Deployment of Advanced Nuclear Reactors /
$c
Kaivalya Mitesh Lal.
264
1
$a
Ann Arbor :
$b
ProQuest Dissertations & Theses,
$c
2024
300
$a
1 electronic resource (658 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: 86-03, Section: B.
500
$a
Advisors: Whittaker, Andrew S. Committee members: Constantinou, Michael C.; Sivaselvan, Mettupalayam V.; Elhami-Khorasani, Negar.
502
$b
Ph.D.
$c
State University of New York at Buffalo
$d
2024.
520
$a
Major impediments to the widespread deployment of new nuclear power plants (NPPs) are high overnight capital cost (OCC) and lengthy time for deployment. The seismic load case is a key driver of the capital cost and longer deployment times and thwarts deployment of standardized reactors as the near-surface geology and seismic hazard are never identical at any two sites. Seismic isolation is a proven, mature technology that offers a means to minimize the effects of earthquake shaking and can enable deployment advanced NPPs with substantially lower OCC and deployment duration. Exploring the role of seismic isolation to enable rapid deployment of new build NPPs is the broad theme of this dissertation, organized into two parts, A and B.The conventional implementation of seismic isolation involves isolating a reactor building at its base. An alternate approach, when building isolation is not practical, involves isolating equipment inside a reactor building. Mid-height seismic isolation of equipment is the focus of Part A of this dissertation: an application not studied previously and considered here to expand the range of options available to designers of safety-class equipment in advanced reactors. It describes proof-of-concept of experiments to investigate the efficacy of mid-height seismic isolation for a tall, slender cylindrical vessel, which could represent a reactor vessel, a steam generator, or a heat exchanger in an advanced nuclear power plant. The carbon steel test article was 20 ft tall with an outer diameter of 5 ft inches and a wall thickness of 1 inch. It was supported near its center of gravity (at its mid-height) on a stiff steel frame using three radial mounts. Three configurations of the vessel were tested: non-isolated, isolated using single Friction Pendulum (SFP) bearings, and isolated using triple Friction Pendulum (TFP) bearings. The vessel was subjected to three component ground motions using a 6 degrees-of-freedom earthquake simulator. The vessel was filled with water during testing to simulate in-service conditions. The test results demonstrated that mid-height seismic isolation enables a significant reduction in horizontal spectral accelerations in the vessel. Numerical models of the non-isolated and isolated vessel were developed, and it was demonstrated that the response of a mid-height isolated tall, slender vessel and its isolation system can be predicted using currently available analysis software. The benchmarked numerical models were used to quantify the benefits of mid-height isolation and demonstrate that the reductions in horizontal spectral accelerations are by-and-large independent of support structure stiffness. Base isolation, although viable, may not be a practical choice for tall, slender equipment because rocking of the vessel may lead to significant changes in axial load on the bearings and possibly axial tension (or uplift in the case of spherical sliding isolators). Mid-height isolation virtually eliminated the rocking response, and with it, the large changes in axial load. Analysis and design recommendations for isolation of equipment in nuclear facilities are also provided.Part B of this dissertation addresses soil-structure-interaction analysis of surface-mounted, seismically isolated advanced reactor buildings. The current rules and guidance for SSI analysis of NPPs are based on the legacy assumption that reactor buildings are both very heavy and stiff: the two key attributes needed for significant SSI on soil sites. Many of the advanced and micro reactors designs (hereafter grouped together as advanced reactors) are one or two orders of magnitude lighter and smaller than their gigawatt-scale predecessors. Reactor developers are considering seismic isolation as a design feature to reduce the impact of the seismic loads, adding flexibility at the reactor building base. The substantial reduction in both weight and stiffness leads to the hypothesis that SSI may have negligible influence on seismically isolated advanced reactors. In a first-of-a-kind study wherein reactor buildings and their safety-class equipment, the supporting soil domains, and nonlinear isolation systems are explicitly modeled and analyzed together, Part B of this dissertation determines whether this hypothesis is correct.An extensive set of response-history analyses was performed for combinations of 1) three fundamentally different advanced reactor buildings, 2) five horizontal isolation systems with a range of linear and bilinear isolator properties, 3) nine seismic inputs covering a range of frequencies and amplitudes of shaking, and 4) seven generic soil profiles that cover a range of sites across the U.S. and were a part of the Design Certification Documents that enabled the KEPCO APR1400 to be certified for use by the USNRC under the 10CFR Part 52 licensing framework, resulting in a total of 945 combinations. The analyses results demonstrated that SSI had negligible no meaningful effect on the in-structure acceleration response of the reactor buildings and the force-displacement behavior of their isolation systems. The peak horizontal displacements of the isolation systems and the peak horizontal accelerations at two locations in each reactor building were essentially identical with and without considering SSI. Using surface-free-field representations of ground shaking for design of surface- (and near-surface-) supported base-isolated advanced reactor buildings, without the need for SSI analysis, is the key recommendation of Part B.
546
$a
English
590
$a
School code: 0656
650
4
$a
Engineering.
$3
586835
650
4
$a
Nuclear engineering.
$3
595435
650
4
$a
Environmental engineering.
$3
548583
653
$a
Advanced nuclear reactors
653
$a
Equipment isolation
653
$a
Safety-class equipment
653
$a
Seismic isolation
653
$a
Soil-structure-interaction
653
$a
Surface free-field motions
690
$a
0543
690
$a
0775
690
$a
0552
690
$a
0537
710
2
$a
State University of New York at Buffalo.
$b
Civil, Structural and Environmental Engineering.
$e
degree granting institution.
$3
3824060
720
1
$a
Whittaker, Andrew S.
$e
degree supervisor.
773
0
$t
Dissertations Abstracts International
$g
86-03B.
790
$a
0656
791
$a
Ph.D.
792
$a
2024
856
4 0
$u
https://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=31555997
based on 0 review(s)
Location:
ALL
電子資源
Year:
Volume Number:
Items
1 records • Pages 1 •
1
Inventory Number
Location Name
Item Class
Material type
Call number
Usage Class
Loan Status
No. of reservations
Opac note
Attachments
W9529864
電子資源
11.線上閱覽_V
電子書
EB
一般使用(Normal)
On shelf
0
1 records • Pages 1 •
1
Multimedia
Reviews
Add a review
and share your thoughts with other readers
Export
pickup library
Processing
...
Change password
Login