DEVELOPMENT OF A GRAPHITE IRRADIATION QUALIFICATION PLAN FOR THE XE-100 REACTOR

Anne A. Campbell; Josina W. Geringer; Adrian M. Schrell; Samuel Baylis; Timothy Lucas; Peter J. Pappano; Martin van Staden

doi:10.1115/PVP2023-106610

DEVELOPMENT OF A GRAPHITE IRRADIATION QUALIFICATION PLAN FOR THE XE-100 REACTOR

Anne A. Campbell, Josina W. Geringer, Adrian M. Schrell, Samuel Baylis, Timothy Lucas, Peter J. Pappano, Martin van Staden

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

The American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III "Rules for Construction of Nuclear Facility Components", Division 5 "High Temperature Reactors", Subsection HH "Class SN Nonmetallic Core Components", Subpart A "Graphite Materials", has a list of materials properties that must be measured and included in the materials data sheet (MDS) for each grade of graphite to be used in a reactor core. Two sections of the MDS includes measuring the effects of degradation, due to oxidation or neutron irradiation damage, on these materials properties. A program at Oak Ridge National Laboratory (ORNL), supported by X Energy, LLC., began in 2017 to produce the irradiation-induced property change results of graphite grades that will be used in the X Energy Xe-100 small modular reactor. Significant effort has been performed around the world to capture these property changes for a range of graphite grades through both the US Advanced Graphite Creep program, and the EU INNOGRAPH/ARCHER program. But both programs were primarily targeted towards higher temperature reactor designs that were of greater importance at the beginning of both programs resulting in a lack of data for temperatures below 600°C. The program at ORNL has been developed to produce the data necessary to assist with completing the irradiation effects on materials properties of the MDS for the graphite grades of interest for X Energy. This paper will discuss the design of the irradiation program including the irradiation conditions (neutron fluence and irradiation temperatures), the types of specimens being used in this program, and the irradiation methodology.

Original language	English
Title of host publication	Codes and Standards
Publisher	American Society of Mechanical Engineers (ASME)
ISBN (Electronic)	9780791887448
DOIs	https://doi.org/10.1115/PVP2023-106610
State	Published - 2023
Event	ASME 2023 Pressure Vessels and Piping Conference, PVP 2023 - Atlanta, United States Duration: Jul 16 2023 → Jul 21 2023

Publication series

Name	American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Volume	1
ISSN (Print)	0277-027X

Conference

Conference	ASME 2023 Pressure Vessels and Piping Conference, PVP 2023
Country/Territory	United States
City	Atlanta
Period	07/16/23 → 07/21/23

Funding

Support for this work was provided by the U.S. Department of Energy, Office of Nuclear Energy via the X-energy Advanced Reactor Concepts (ARC) 15 Award. Oak Ridge National Laboratory is managed by UT-Battelle, LLC, under contract No. DE-AC05-00OR22725 for the U.S. Department of Energy. *This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).

Keywords

ASME Code Qualification
Irradiation effects
Nuclear graphite

Access to Document

10.1115/PVP2023-106610

Cite this

Campbell, A. A., Geringer, J. W., Schrell, A. M., Baylis, S., Lucas, T., Pappano, P. J., & van Staden, M. (2023). DEVELOPMENT OF A GRAPHITE IRRADIATION QUALIFICATION PLAN FOR THE XE-100 REACTOR. In Codes and Standards Article v001t01a049 (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP; Vol. 1). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/PVP2023-106610

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title = "DEVELOPMENT OF A GRAPHITE IRRADIATION QUALIFICATION PLAN FOR THE XE-100 REACTOR",

abstract = "The American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III {"}Rules for Construction of Nuclear Facility Components{"}, Division 5 {"}High Temperature Reactors{"}, Subsection HH {"}Class SN Nonmetallic Core Components{"}, Subpart A {"}Graphite Materials{"}, has a list of materials properties that must be measured and included in the materials data sheet (MDS) for each grade of graphite to be used in a reactor core. Two sections of the MDS includes measuring the effects of degradation, due to oxidation or neutron irradiation damage, on these materials properties. A program at Oak Ridge National Laboratory (ORNL), supported by X Energy, LLC., began in 2017 to produce the irradiation-induced property change results of graphite grades that will be used in the X Energy Xe-100 small modular reactor. Significant effort has been performed around the world to capture these property changes for a range of graphite grades through both the US Advanced Graphite Creep program, and the EU INNOGRAPH/ARCHER program. But both programs were primarily targeted towards higher temperature reactor designs that were of greater importance at the beginning of both programs resulting in a lack of data for temperatures below 600°C. The program at ORNL has been developed to produce the data necessary to assist with completing the irradiation effects on materials properties of the MDS for the graphite grades of interest for X Energy. This paper will discuss the design of the irradiation program including the irradiation conditions (neutron fluence and irradiation temperatures), the types of specimens being used in this program, and the irradiation methodology.",

keywords = "ASME Code Qualification, Irradiation effects, Nuclear graphite",

author = "Campbell, {Anne A.} and Geringer, {Josina W.} and Schrell, {Adrian M.} and Samuel Baylis and Timothy Lucas and Pappano, {Peter J.} and {van Staden}, Martin",

note = "Publisher Copyright: Copyright {\textcopyright} 2023 by The United States Government.; ASME 2023 Pressure Vessels and Piping Conference, PVP 2023 ; Conference date: 16-07-2023 Through 21-07-2023",

year = "2023",

doi = "10.1115/PVP2023-106610",

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Campbell, AA, Geringer, JW, Schrell, AM, Baylis, S, Lucas, T, Pappano, PJ & van Staden, M 2023, DEVELOPMENT OF A GRAPHITE IRRADIATION QUALIFICATION PLAN FOR THE XE-100 REACTOR. in Codes and Standards., v001t01a049, American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP, vol. 1, American Society of Mechanical Engineers (ASME), ASME 2023 Pressure Vessels and Piping Conference, PVP 2023, Atlanta, United States, 07/16/23. https://doi.org/10.1115/PVP2023-106610

DEVELOPMENT OF A GRAPHITE IRRADIATION QUALIFICATION PLAN FOR THE XE-100 REACTOR. / Campbell, Anne A.; Geringer, Josina W.; Schrell, Adrian M. et al.
Codes and Standards. American Society of Mechanical Engineers (ASME), 2023. v001t01a049 (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP; Vol. 1).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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T1 - DEVELOPMENT OF A GRAPHITE IRRADIATION QUALIFICATION PLAN FOR THE XE-100 REACTOR

AU - Campbell, Anne A.

AU - Geringer, Josina W.

AU - Schrell, Adrian M.

AU - Baylis, Samuel

AU - Lucas, Timothy

AU - Pappano, Peter J.

AU - van Staden, Martin

PY - 2023

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N2 - The American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III "Rules for Construction of Nuclear Facility Components", Division 5 "High Temperature Reactors", Subsection HH "Class SN Nonmetallic Core Components", Subpart A "Graphite Materials", has a list of materials properties that must be measured and included in the materials data sheet (MDS) for each grade of graphite to be used in a reactor core. Two sections of the MDS includes measuring the effects of degradation, due to oxidation or neutron irradiation damage, on these materials properties. A program at Oak Ridge National Laboratory (ORNL), supported by X Energy, LLC., began in 2017 to produce the irradiation-induced property change results of graphite grades that will be used in the X Energy Xe-100 small modular reactor. Significant effort has been performed around the world to capture these property changes for a range of graphite grades through both the US Advanced Graphite Creep program, and the EU INNOGRAPH/ARCHER program. But both programs were primarily targeted towards higher temperature reactor designs that were of greater importance at the beginning of both programs resulting in a lack of data for temperatures below 600°C. The program at ORNL has been developed to produce the data necessary to assist with completing the irradiation effects on materials properties of the MDS for the graphite grades of interest for X Energy. This paper will discuss the design of the irradiation program including the irradiation conditions (neutron fluence and irradiation temperatures), the types of specimens being used in this program, and the irradiation methodology.

AB - The American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III "Rules for Construction of Nuclear Facility Components", Division 5 "High Temperature Reactors", Subsection HH "Class SN Nonmetallic Core Components", Subpart A "Graphite Materials", has a list of materials properties that must be measured and included in the materials data sheet (MDS) for each grade of graphite to be used in a reactor core. Two sections of the MDS includes measuring the effects of degradation, due to oxidation or neutron irradiation damage, on these materials properties. A program at Oak Ridge National Laboratory (ORNL), supported by X Energy, LLC., began in 2017 to produce the irradiation-induced property change results of graphite grades that will be used in the X Energy Xe-100 small modular reactor. Significant effort has been performed around the world to capture these property changes for a range of graphite grades through both the US Advanced Graphite Creep program, and the EU INNOGRAPH/ARCHER program. But both programs were primarily targeted towards higher temperature reactor designs that were of greater importance at the beginning of both programs resulting in a lack of data for temperatures below 600°C. The program at ORNL has been developed to produce the data necessary to assist with completing the irradiation effects on materials properties of the MDS for the graphite grades of interest for X Energy. This paper will discuss the design of the irradiation program including the irradiation conditions (neutron fluence and irradiation temperatures), the types of specimens being used in this program, and the irradiation methodology.

KW - ASME Code Qualification

KW - Irradiation effects

KW - Nuclear graphite

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Campbell AA, Geringer JW, Schrell AM, Baylis S, Lucas T, Pappano PJ et al. DEVELOPMENT OF A GRAPHITE IRRADIATION QUALIFICATION PLAN FOR THE XE-100 REACTOR. In Codes and Standards. American Society of Mechanical Engineers (ASME). 2023. v001t01a049. (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP). doi: 10.1115/PVP2023-106610

DEVELOPMENT OF A GRAPHITE IRRADIATION QUALIFICATION PLAN FOR THE XE-100 REACTOR

Abstract

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Funding

Keywords

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