RAMTAR Research - Revision history

Admin: 2 revisions imported

2025-01-24T18:23:32Z

2 revisions imported

← Older revision	Revision as of 18:23, 24 January 2025
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Admin at 18:16, 24 January 2025

2025-01-24T18:16:38Z

← Older revision	Revision as of 18:16, 24 January 2025
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Admin: /* Ongoing Research on Advanced Reactor Risk Assessment Methods and Tools – List of Active Project Topics */

2025-01-17T21:43:15Z

Ongoing Research on Advanced Reactor Risk Assessment Methods and Tools – List of Active Project Topics

← Older revision		Revision as of 21:43, 17 January 2025
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	[[Human Reliability Analysis\|4 - HRA]]		[[Human Reliability Analysis\|4 - HRA]]

	Human Reliability Analysis plays a large role in identifying not only possible failures caused by plant personnel failing to follow plant procedures, but also ways in which operators can mitigate plant failures preventing an accident. Since there are no current plant procedures for advanced reactors this will present additional challenges and may even require a different methodology than what has been used for HRA applied to ~~LWRs~~.		Human Reliability Analysis plays a large role in identifying not only possible failures caused by plant personnel failing to follow plant procedures, but also ways in which operators can mitigate plant failures preventing an accident. Since there are no current plant procedures for advanced reactors this will present additional challenges and may even require a different methodology than what has been used for HRA applied to water reactors.
	<br><br>		<br><br>
	[[Data\|5 - Data]]		[[Data\|5 - Data]]

Admin: /* Ongoing Research on Advanced Reactor Risk Assessment Methods and Tools – List of Active Project Topics */

2025-01-17T21:42:45Z

Ongoing Research on Advanced Reactor Risk Assessment Methods and Tools – List of Active Project Topics

← Older revision		Revision as of 21:42, 17 January 2025
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	[[Risk Metrics\|1 - Risk Metrics]]		[[Risk Metrics\|1 - Risk Metrics]]

	Risk metrics currently used for ~~LWRs~~ may not necessarily be applicable to advanced reactors depending on the specific advanced reactor design. There are currently a range of different solutions being investigated such as generalizing the CDF definition and/or applying the definition to become plant specific, or creating new risk metrics that are specific to plant characteristics such as mission or possible impact.		Risk metrics currently used for water reactors may not necessarily be applicable to advanced reactors depending on the specific advanced reactor design. There are currently a range of different solutions being investigated such as generalizing the CDF definition and/or applying the definition to become plant specific, or creating new risk metrics that are specific to plant characteristics such as mission or possible impact.
	<br><br>		<br><br>
	[[Passive Safety System Reliability\|2 - Passive Safety System Reliability]]		[[Passive Safety System Reliability\|2 - Passive Safety System Reliability]]
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	Human Reliability Analysis plays a large role in identifying not only possible failures caused by plant personnel failing to follow plant procedures, but also ways in which operators can mitigate plant failures preventing an accident. Since there are no current plant procedures for advanced reactors this will present additional challenges and may even require a different methodology than what has been used for HRA applied to LWRs.		Human Reliability Analysis plays a large role in identifying not only possible failures caused by plant personnel failing to follow plant procedures, but also ways in which operators can mitigate plant failures preventing an accident. Since there are no current plant procedures for advanced reactors this will present additional challenges and may even require a different methodology than what has been used for HRA applied to LWRs.
	<br><br>		<br><br>
	[[~~PRA~~ Data\|5 - ~~PRA~~ Data]]		[[Data\|5 - Data]]

	This research activity will focus on identification of data and relevant characteristics necessary to support plant safety analysis and plant risk assessments that will be used for plant licensing submittals and operational decision-making.		This research activity will focus on identification of data and relevant characteristics necessary to support plant safety analysis and plant risk assessments that will be used for plant licensing submittals and operational decision-making.

Admin at 15:39, 17 July 2024

2024-07-17T15:39:41Z

← Older revision		Revision as of 15:39, 17 July 2024
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	Human Reliability Analysis plays a large role in identifying not only possible failures caused by plant personnel failing to follow plant procedures, but also ways in which operators can mitigate plant failures preventing an accident. Since there are no current plant procedures for advanced reactors this will present additional challenges and may even require a different methodology than what has been used for HRA applied to LWRs.		Human Reliability Analysis plays a large role in identifying not only possible failures caused by plant personnel failing to follow plant procedures, but also ways in which operators can mitigate plant failures preventing an accident. Since there are no current plant procedures for advanced reactors this will present additional challenges and may even require a different methodology than what has been used for HRA applied to LWRs.
	<br><br>		<br><br>
	[[PRA Data\|5 - Data]]		[[PRA Data\|5 - PRA Data]]

	This research activity will focus on identification of data and relevant characteristics necessary to support plant safety analysis and plant risk assessments that will be used for plant licensing submittals and operational decision-making.		This research activity will focus on identification of data and relevant characteristics necessary to support plant safety analysis and plant risk assessments that will be used for plant licensing submittals and operational decision-making.

Admin at 15:39, 17 July 2024

2024-07-17T15:39:27Z

← Older revision		Revision as of 15:39, 17 July 2024
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	Human Reliability Analysis plays a large role in identifying not only possible failures caused by plant personnel failing to follow plant procedures, but also ways in which operators can mitigate plant failures preventing an accident. Since there are no current plant procedures for advanced reactors this will present additional challenges and may even require a different methodology than what has been used for HRA applied to LWRs.		Human Reliability Analysis plays a large role in identifying not only possible failures caused by plant personnel failing to follow plant procedures, but also ways in which operators can mitigate plant failures preventing an accident. Since there are no current plant procedures for advanced reactors this will present additional challenges and may even require a different methodology than what has been used for HRA applied to LWRs.
	<br><br>		<br><br>
	[[Data\|5 - Data]]		[[PRA Data\|5 - Data]]

	This research activity will focus on identification of data and relevant characteristics necessary to support plant safety analysis and plant risk assessments that will be used for plant licensing submittals and operational decision-making.		This research activity will focus on identification of data and relevant characteristics necessary to support plant safety analysis and plant risk assessments that will be used for plant licensing submittals and operational decision-making.

Admin: /* Objective / Purpose */

2024-07-10T16:04:15Z

Objective / Purpose

← Older revision		Revision as of 16:04, 10 July 2024
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	==Objective / Purpose==		==Objective / Purpose==
	Given the state of development and plans for licensing / deployment of advanced reactors, RAMTAR research aims prioritize ~~identifying~~ and ~~conducting~~ research to address gaps that support near-term licensing actions for advanced reactors.		Given the state of development and plans for licensing / deployment of advanced reactors, RAMTAR research aims to prioritize the identification and implementation of research to address gaps that support near-term licensing actions for advanced reactors.

	==Scope==		==Scope==

Admin: /* Ongoing Research on Advanced Reactor Risk Assessment Methods and Tools – List of Active Project Topics */

2024-07-09T18:50:45Z

Ongoing Research on Advanced Reactor Risk Assessment Methods and Tools – List of Active Project Topics

← Older revision		Revision as of 18:50, 9 July 2024
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	[[Risk Metrics\|1 - Risk Metrics]]		[[Risk Metrics\|1 - Risk Metrics]]

	Risk metrics currently used for LWRs may not necessarily be applicable to ~~AR's~~ depending on the specific AR design. There are currently a range of different solutions being investigated such as generalizing the CDF definition and/or applying the definition to become plant specific, or creating new risk metrics that are specific to plant characteristics such as mission or possible impact.		Risk metrics currently used for LWRs may not necessarily be applicable to advanced reactors depending on the specific advanced reactor design. There are currently a range of different solutions being investigated such as generalizing the CDF definition and/or applying the definition to become plant specific, or creating new risk metrics that are specific to plant characteristics such as mission or possible impact.
	<br><br>		<br><br>
	[[Passive Safety System Reliability\|2 - Passive Safety System Reliability]]		[[Passive Safety System Reliability\|2 - Passive Safety System Reliability]]

Admin: /* Scope */

2024-06-19T22:04:15Z

Scope

← Older revision		Revision as of 22:04, 19 June 2024
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	==Scope==		==Scope==
	Research topics are aligned with identification and assessment of issues related to the definition, execution, and application of PRAs to the design, licensing, construction, and operation of advanced reactors. Research topics include what is shown in Figure 1 on the landing page.		Research topics are aligned with identification and assessment of issues related to the definition, execution, and application of PRAs to the design, licensing, construction, and operation of advanced reactors. The topics listed below are limited to active or future research as part of EPRI’s Advanced Reactors research initiatives. Additional research on these topics is also being conducted by other organizations (i.e., the list is not intended to be all encompassing). Research topics include what is shown in Figure 1 on the landing page.

	==Ongoing Research on Advanced Reactor Risk Assessment Methods and Tools – List of Active Project Topics==		==Ongoing Research on Advanced Reactor Risk Assessment Methods and Tools – List of Active Project Topics==

Admin: /* Ongoing Research on Advanced Reactor Risk Assessment Methods and Tools – List of Active Project Topics */

2024-06-12T21:28:03Z

Ongoing Research on Advanced Reactor Risk Assessment Methods and Tools – List of Active Project Topics

← Older revision		Revision as of 21:28, 12 June 2024
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	[[Passive Safety System Reliability\|2 - Passive Safety System Reliability]]		[[Passive Safety System Reliability\|2 - Passive Safety System Reliability]]

	Passive safety systems (PSSs) will serve as a cornerstone requirement for the licensing of advanced nuclear ~~generating~~ plants. Having a reliance on safety systems that are passive, that is, those that rely on natural physical laws and require minimal or no intervention by plant operators provides a significant reduction in the probability of a serious accident.		Passive safety systems (PSSs) will serve as a cornerstone requirement for the licensing of advanced nuclear reactor plants. Having a reliance on safety systems that are passive, that is, those that rely on natural/physical laws and require minimal or no intervention by plant operators provides a significant reduction in the probability of a serious accident.
	<br><br>		<br><br>
	[[External Hazards\|3 - External Hazards]]		[[External Hazards\|3 - External Hazards]]
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	[[Human Reliability Analysis\|4 - HRA]]		[[Human Reliability Analysis\|4 - HRA]]

	Human Reliability Analysis plays a large role in identifying not only possible failures caused by plant personnel failing to follow plant procedures, but also ways in which operators can mitigate plant failures preventing an accident. Since there are no current plant procedures for ~~advance~~ reactors this will present additional challenges and may even require a different methodology than what has been used for HRA applied to LWRs.		Human Reliability Analysis plays a large role in identifying not only possible failures caused by plant personnel failing to follow plant procedures, but also ways in which operators can mitigate plant failures preventing an accident. Since there are no current plant procedures for advanced reactors this will present additional challenges and may even require a different methodology than what has been used for HRA applied to LWRs.
	<br><br>		<br><br>
	[[Data\|5 - Data]]		[[Data\|5 - Data]]