ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature ReactorsSource: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 004::page 041106-1DOI: 10.1115/1.4047113Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The mission of the U.S. Department of Energy (DOE), Office of Nuclear Energy is to advance nuclear power in order to meet the nation's energy, environmental, and energy security needs. Advanced high temperature reactor systems will require compact heat exchangers (CHXs) for the next generation of nuclear reactors. The DOE is sponsoring research to support the development and deployment of CHXs for use in high temperature advanced reactors. The project is being executed by an Integrated Research Project (IRP) that includes university research institutes, national laboratories, manufacturers, and industry experts. The objective is to enable the use of CHX designs in advanced reactor service. A necessary step for achieving this objective is to ensure that the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section III, Division 5 has rules for the construction of CHXs for nuclear service. However, construction rules alone are not sufficient to deploy a CHX in an advanced reactor. A strategy for ASME Boiler and Pressure Vessel Code, Section XI, Inservice Inspection (ISI) of a heat exchanger in an operating nuclear reactor will also be required. The purpose of this ASME Code Roadmap is to identify the research gaps impeding the development of suitable construction and ISI rules for CHXs for high temperature reactor service and to provide a framework to utilize the research project results consistent with the expectations and needs of the industry and future owners.
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contributor author | Keating, Robert B. | |
contributor author | McKillop, Suzanne P. | |
contributor author | Allen, Todd | |
contributor author | Anderson, Mark | |
date accessioned | 2022-02-04T22:16:33Z | |
date available | 2022-02-04T22:16:33Z | |
date copyright | 9/4/2020 12:00:00 AM | |
date issued | 2020 | |
identifier issn | 2332-8983 | |
identifier other | ners_006_04_041106.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4275238 | |
description abstract | The mission of the U.S. Department of Energy (DOE), Office of Nuclear Energy is to advance nuclear power in order to meet the nation's energy, environmental, and energy security needs. Advanced high temperature reactor systems will require compact heat exchangers (CHXs) for the next generation of nuclear reactors. The DOE is sponsoring research to support the development and deployment of CHXs for use in high temperature advanced reactors. The project is being executed by an Integrated Research Project (IRP) that includes university research institutes, national laboratories, manufacturers, and industry experts. The objective is to enable the use of CHX designs in advanced reactor service. A necessary step for achieving this objective is to ensure that the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section III, Division 5 has rules for the construction of CHXs for nuclear service. However, construction rules alone are not sufficient to deploy a CHX in an advanced reactor. A strategy for ASME Boiler and Pressure Vessel Code, Section XI, Inservice Inspection (ISI) of a heat exchanger in an operating nuclear reactor will also be required. The purpose of this ASME Code Roadmap is to identify the research gaps impeding the development of suitable construction and ISI rules for CHXs for high temperature reactor service and to provide a framework to utilize the research project results consistent with the expectations and needs of the industry and future owners. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors | |
type | Journal Paper | |
journal volume | 6 | |
journal issue | 4 | |
journal title | Journal of Nuclear Engineering and Radiation Science | |
identifier doi | 10.1115/1.4047113 | |
journal fristpage | 041106-1 | |
journal lastpage | 041106-9 | |
page | 9 | |
tree | Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 004 | |
contenttype | Fulltext |