Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Seismic isolation has been shown to be able to reduce transmitted seismic force and lower response accelerations of a structure. When applied to nuclear reactors, it will minimize seismic influence on the reactor design and provide a design which is less site dependent. In liquid metal reactors where components are virtually at atmospheric pressure but under severe thermal conditions, thin-walled structures are generally used for primary systems. Thin-walled structures, however, have little inherent seismic resistance. The concept of seismic isolation therefore offers a viable and effective approach that permits the reactor structures to better withstand thermal and seismic loadings simultaneously. The majority of published work on seismic isolation deals with use of horizontal isolation system only. In this investigation, however, local vertical isolation is also provided for the primary system. Such local vertical isolation is found to result in significant benefits for major massive components, such as the reactor cover, designed to withstand vertical motions and loadings. Preliminary estimations on commodity savings of the primary system show that, with additional local vertical isolation, the savings could be twice that estimated for horizontal isolation only. The degree of effectiveness of vertical isolation depends on the diameter of the reactor vessel. As the reactor vessel diameter increases, the vertical seismic effects become more pronounced and vertical isolation can make a significant contribution.
Benefits of Vertical and Horizontal Seismic Isolation for LMR (liquid Metal Reactor) Nuclear Reactor Units
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Seismic isolation has been shown to be able to reduce transmitted seismic force and lower response accelerations of a structure. When applied to nuclear reactors, it will minimize seismic influence on the reactor design and provide a design which is less site dependent. In liquid metal reactors where components are virtually at atmospheric pressure but under severe thermal conditions, thin-walled structures are generally used for primary systems. Thin-walled structures, however, have little inherent seismic resistance. The concept of seismic isolation therefore offers a viable and effective approach that permits the reactor structures to better withstand thermal and seismic loadings simultaneously. The majority of published work on seismic isolation deals with use of horizontal isolation system only. In this investigation, however, local vertical isolation is also provided for the primary system. Such local vertical isolation is found to result in significant benefits for major massive components, such as the reactor cover, designed to withstand vertical motions and loadings. Preliminary estimations on commodity savings of the primary system show that, with additional local vertical isolation, the savings could be twice that estimated for horizontal isolation only. The degree of effectiveness of vertical isolation depends on the diameter of the reactor vessel. As the reactor vessel diameter increases, the vertical seismic effects become more pronounced and vertical isolation can make a significant contribution.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Seismic isolation has been shown to be able to reduce transmitted seismic force and lower response accelerations of a structure. When applied to nuclear reactors, it will minimize seismic influence on the reactor design and provide a design which is less site dependent. In liquid metal reactors where components are virtually at atmospheric pressure but under severe thermal conditions, thin-walled structures are generally used for primary systems. Thin-walled structures, however, have little inherent seismic resistance. The concept of seismic isolation therefore offers a viable and effective approach that permits the reactor structures to better withstand thermal and seismic loadings simultaneously. The majority of published work on seismic isolation deals with use of horizontal isolation system only. In this investigation, however, local vertical isolation is also provided for the primary system. Such local vertical isolation is found to result in significant benefits for major massive components, such as the reactor cover, designed to withstand vertical motions and loadings. Preliminary estimations on commodity savings of the primary system show that, with additional local vertical isolation, the savings could be twice that estimated for horizontal isolation only. The degree of effectiveness of vertical isolation depends on the diameter of the reactor vessel. As the reactor vessel diameter increases, the vertical seismic effects become more pronounced and vertical isolation can make a significant contribution.
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 840
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 840
Book Description
Response of a Base-isolated Large Liquid Metal Reactor Plant to Seismic Loads
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 6
Book Description
In recent years, base isolation has been applied to various civil structures such as bridges and buildings for the purpose of reducing its acceleration to below the level of ground accelerations during seismic events. The basic principal of base isolation is to introduce a soft layer of material between structure foundation to allow a degree of flexibility in horizontal motions which could reduce the seismic accelerations during earthquakes. If base isolation is properly designed, it shifts the fundamental frequency of the structure away from the damaging frequency range of earthquakes. Thus, the seismic loads transmitted to the structure can be greatly reduced. This is particularly important in Liquid Metal Reactor (LMR) plants, because the components of primary system such as reactor vessel and piping loops are designed to be thin-walled structures and have little inherent seismic resistance. Thus, the use of base isolation offers a viable and effective approach that permits the reactor structures to better withstand the seismic loading. This paper deals with the seismic response of a base isolated large-scale LMR plant. The analysis model was based on a preliminary nuclear island layout developed by EPRI during the concept development phase of the large-scale prototype breeder (LSPB) project. The nuclear island has a dimension of 184'-0'' x 210'-6''; the reactor vessel has an ID of 62 ft and an overall length of 70 ft. Two soil conditions have been considered in the analysis. One is a hard-soil site having a shear wave velocity of 6000 ft/s, and the other is a soft-soil site having a shear wave velocity of 2000 ft/s. For comparison purposes, the responses of a conventional plant (unisolated) was also analyzed. 3 figs., 1 tab.
Publisher:
ISBN:
Category :
Languages : en
Pages : 6
Book Description
In recent years, base isolation has been applied to various civil structures such as bridges and buildings for the purpose of reducing its acceleration to below the level of ground accelerations during seismic events. The basic principal of base isolation is to introduce a soft layer of material between structure foundation to allow a degree of flexibility in horizontal motions which could reduce the seismic accelerations during earthquakes. If base isolation is properly designed, it shifts the fundamental frequency of the structure away from the damaging frequency range of earthquakes. Thus, the seismic loads transmitted to the structure can be greatly reduced. This is particularly important in Liquid Metal Reactor (LMR) plants, because the components of primary system such as reactor vessel and piping loops are designed to be thin-walled structures and have little inherent seismic resistance. Thus, the use of base isolation offers a viable and effective approach that permits the reactor structures to better withstand the seismic loading. This paper deals with the seismic response of a base isolated large-scale LMR plant. The analysis model was based on a preliminary nuclear island layout developed by EPRI during the concept development phase of the large-scale prototype breeder (LSPB) project. The nuclear island has a dimension of 184'-0'' x 210'-6''; the reactor vessel has an ID of 62 ft and an overall length of 70 ft. Two soil conditions have been considered in the analysis. One is a hard-soil site having a shear wave velocity of 6000 ft/s, and the other is a soft-soil site having a shear wave velocity of 2000 ft/s. For comparison purposes, the responses of a conventional plant (unisolated) was also analyzed. 3 figs., 1 tab.
ERDA Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 848
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 848
Book Description
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 908
Book Description
Includes all works deriving from DOE, other related government-sponsored information and foreign nonnuclear information.
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 908
Book Description
Includes all works deriving from DOE, other related government-sponsored information and foreign nonnuclear information.
Response of a Pool-type LMR (liquid Metal Reactor) to Seismic Loads
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 6
Book Description
This paper describes the seismic analysis of a 450-MWe pool-type liquid metal reactor (LMR) under 0.3 g SSE ground excitations. It also assess the ultimate inelastic structural capabilities for other beyond-design-basis seismic events. Calculation is focused on a new design configuration where the vessel thickness is reduced considerably compared to the previous design (Ma and Gvildys, 1987). In the analysis, the stress and displacement fields at important locations of the reactor vessel, guard vessel, and support skirt are investigated. Emphasis is placed on the horizontal excitation in which large stress is generated. The possibility of impact between the reactor and guard vessels is examined. In the reactor vessel analysis, the effect of fluid-structure interaction is included. Attention is further given to the maximum horizontal acceleration of the reactor core as well as the relative displacement between the reactor core and the upper internal structure. The Argonne National Laboratory augmented three-dimensional Fluid-Structure Interaction program, FLUSTR-ANL is utilized for performing the base calculation where ground excitation is assumed to be 0.3 g SSE. The Newmark-Hall Ductility modification method was used for the beyond-design-basis seismic events. In both calculations, stress fields generated from the horizontal and vertical excitations are evaluated separately. The resultant stresses due to combined actions of these events are computed by the SRSS method. 4 refs., 5 figs., 2 tabs.
Publisher:
ISBN:
Category :
Languages : en
Pages : 6
Book Description
This paper describes the seismic analysis of a 450-MWe pool-type liquid metal reactor (LMR) under 0.3 g SSE ground excitations. It also assess the ultimate inelastic structural capabilities for other beyond-design-basis seismic events. Calculation is focused on a new design configuration where the vessel thickness is reduced considerably compared to the previous design (Ma and Gvildys, 1987). In the analysis, the stress and displacement fields at important locations of the reactor vessel, guard vessel, and support skirt are investigated. Emphasis is placed on the horizontal excitation in which large stress is generated. The possibility of impact between the reactor and guard vessels is examined. In the reactor vessel analysis, the effect of fluid-structure interaction is included. Attention is further given to the maximum horizontal acceleration of the reactor core as well as the relative displacement between the reactor core and the upper internal structure. The Argonne National Laboratory augmented three-dimensional Fluid-Structure Interaction program, FLUSTR-ANL is utilized for performing the base calculation where ground excitation is assumed to be 0.3 g SSE. The Newmark-Hall Ductility modification method was used for the beyond-design-basis seismic events. In both calculations, stress fields generated from the horizontal and vertical excitations are evaluated separately. The resultant stresses due to combined actions of these events are computed by the SRSS method. 4 refs., 5 figs., 2 tabs.
Seismic, Shock, and Vibration Isolation, 1990
Author: Howard Chung
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 68
Book Description
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 68
Book Description
INIS Atomindex
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 962
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 962
Book Description
Evaluation of LMR (liquid Metal Reactors) Core Support Concepts Under Seismic Events
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
In the design of the core support system for liquid metal reactors (LMR) against earthquakes, the major concerns are directed toward the structural integrity as well as the reactivity control. This means that, in addition to the stress levels, maximum displacements and accelerations should also be within their allowable limits. This investigation studies the seismic responses of a large pool-type LMR with different design approaches to support the reactor core. Different core support designs yield different frequency ranges and responses. Responses of these designs to the given floor response spectra are required to satisfy a set of criteria which are common to all designs. 5 refs., 4 figs.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
In the design of the core support system for liquid metal reactors (LMR) against earthquakes, the major concerns are directed toward the structural integrity as well as the reactivity control. This means that, in addition to the stress levels, maximum displacements and accelerations should also be within their allowable limits. This investigation studies the seismic responses of a large pool-type LMR with different design approaches to support the reactor core. Different core support designs yield different frequency ranges and responses. Responses of these designs to the given floor response spectra are required to satisfy a set of criteria which are common to all designs. 5 refs., 4 figs.
Government Reports Annual Index
Author:
Publisher:
ISBN:
Category : Research
Languages : en
Pages : 1428
Book Description
Sections 1-2. Keyword Index.--Section 3. Personal author index.--Section 4. Corporate author index.-- Section 5. Contract/grant number index, NTIS order/report number index 1-E.--Section 6. NTIS order/report number index F-Z.
Publisher:
ISBN:
Category : Research
Languages : en
Pages : 1428
Book Description
Sections 1-2. Keyword Index.--Section 3. Personal author index.--Section 4. Corporate author index.-- Section 5. Contract/grant number index, NTIS order/report number index 1-E.--Section 6. NTIS order/report number index F-Z.