RELAP5-3D Modeling in the OECD-NEA HTTF Benchmark

Robert Forrester Kile

RELAP5-3D Modeling in the OECD-NEA HTTF Benchmark

Robert Forrester Kile

Nuclear Reactor Technology

Research output: Contribution to conference › Presentation

Abstract

Prismatic gas-cooled reactors are a technologically mature reactor concept of interest for near- to mid-term deployment. To accelerate the deployment of these reactors, the DOE's Advanced Reactor Technologies Gas-Cooled Reactor campaign is spearheading a thermal hydraulics code validation benchmark based on the High Temperature Test Facility at Oregon State University. This presentation provides an introduction to that benchmark and an overview of some of the RELAP5-3D validation activities stemming from that benchmark.

Original language	English
State	Published - 2023
Event	International RELAP5-3D User's Group Meeting - Idaho Falls, United States Duration: Dec 7 2023 → Dec 8 2023

Conference

Conference	International RELAP5-3D User's Group Meeting
Country/Territory	United States
City	Idaho Falls
Period	12/7/23 → 12/8/23

Keywords

22 - GENERAL STUDIES OF NUCLEAR REACTORS
RELAP5-3D
validation
HTGR
thermal hydraulics
HTTF

INL Publication Number

INL/CON-23-75691
165725

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title = "RELAP5-3D Modeling in the OECD-NEA HTTF Benchmark",

abstract = "Prismatic gas-cooled reactors are a technologically mature reactor concept of interest for near- to mid-term deployment. To accelerate the deployment of these reactors, the DOE's Advanced Reactor Technologies Gas-Cooled Reactor campaign is spearheading a thermal hydraulics code validation benchmark based on the High Temperature Test Facility at Oregon State University. This presentation provides an introduction to that benchmark and an overview of some of the RELAP5-3D validation activities stemming from that benchmark.",

keywords = "22 - GENERAL STUDIES OF NUCLEAR REACTORS, RELAP5-3D, validation, HTGR, thermal hydraulics, HTTF",

author = "Kile, \{Robert Forrester\}",

year = "2023",

language = "English",

note = "International RELAP5-3D User's Group Meeting ; Conference date: 07-12-2023 Through 08-12-2023",

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TY - CONF

T1 - RELAP5-3D Modeling in the OECD-NEA HTTF Benchmark

AU - Kile, Robert Forrester

PY - 2023

Y1 - 2023

N2 - Prismatic gas-cooled reactors are a technologically mature reactor concept of interest for near- to mid-term deployment. To accelerate the deployment of these reactors, the DOE's Advanced Reactor Technologies Gas-Cooled Reactor campaign is spearheading a thermal hydraulics code validation benchmark based on the High Temperature Test Facility at Oregon State University. This presentation provides an introduction to that benchmark and an overview of some of the RELAP5-3D validation activities stemming from that benchmark.

AB - Prismatic gas-cooled reactors are a technologically mature reactor concept of interest for near- to mid-term deployment. To accelerate the deployment of these reactors, the DOE's Advanced Reactor Technologies Gas-Cooled Reactor campaign is spearheading a thermal hydraulics code validation benchmark based on the High Temperature Test Facility at Oregon State University. This presentation provides an introduction to that benchmark and an overview of some of the RELAP5-3D validation activities stemming from that benchmark.

KW - 22 - GENERAL STUDIES OF NUCLEAR REACTORS

KW - RELAP5-3D

KW - validation

KW - HTGR

KW - thermal hydraulics

KW - HTTF

M3 - Presentation

T2 - International RELAP5-3D User's Group Meeting

Y2 - 7 December 2023 through 8 December 2023

ER -

RELAP5-3D Modeling in the OECD-NEA HTTF Benchmark

Abstract

Conference

Keywords

INL Publication Number

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