BISON Validation for LOCA and PCMI Behaviour Using Measurements From the Halden Reactor Project

RL Williamson; G Pastore; BW Spencer; JD Hales; T Tverberg

BISON Validation for LOCA and PCMI Behaviour Using Measurements From the Halden Reactor Project

RL Williamson
, G Pastore
, BW Spencer
, JD Hales
, T Tverberg

Research output: Contribution to conference › Paper

Abstract

BISON is a finite element-based nuclear fuel performance code that has been under development at Idaho National Laboratory (INL) since 2009. The code is applicable to both steady and transient fuel behavior and has been used to analyze a variety of fuel forms in 1D spherical, 1.5D and 2D axisymmetric, or 3D geometries. Efforts are underway to validate BISON for application to Light Water Reactor fuels using, to a large extent, experimental data from the Halden Reactor Project. Recent validation activities have included both Loss of Coolant Accident (LOCA) and Pellet Clad Mechanical Interaction (PCMI) experiments. Two such validation cases, the IFA-650.10 LOCA test and the IFA-629.4 power ramp test (PCMI), are summarized in this paper.

Original language	English
State	Published - Sep 1 2017
Event	EHPG 2017 - The 40th Enlarged Halden Program Group Meeting - Lillehammer, Norway Duration: Sep 24 2017 → Sep 29 2017

Conference

Conference	EHPG 2017 - The 40th Enlarged Halden Program Group Meeting
Country/Territory	Norway
City	Lillehammer
Period	09/24/17 → 09/29/17

Keywords

BISON
Halden Reactor Project
validation

INL Publication Number

INL/CON-17-42169
33519

Access to Document

https://www.osti.gov/servlets/purl/1414448

Cite this

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title = "BISON Validation for LOCA and PCMI Behaviour Using Measurements From the Halden Reactor Project",

abstract = "BISON is a finite element-based nuclear fuel performance code that has been under development at Idaho National Laboratory (INL) since 2009. The code is applicable to both steady and transient fuel behavior and has been used to analyze a variety of fuel forms in 1D spherical, 1.5D and 2D axisymmetric, or 3D geometries. Efforts are underway to validate BISON for application to Light Water Reactor fuels using, to a large extent, experimental data from the Halden Reactor Project. Recent validation activities have included both Loss of Coolant Accident (LOCA) and Pellet Clad Mechanical Interaction (PCMI) experiments. Two such validation cases, the IFA-650.10 LOCA test and the IFA-629.4 power ramp test (PCMI), are summarized in this paper.",

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author = "RL Williamson and G Pastore and BW Spencer and JD Hales and T Tverberg",

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note = "EHPG 2017 - The 40th Enlarged Halden Program Group Meeting ; Conference date: 24-09-2017 Through 29-09-2017",

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TY - CONF

T1 - BISON Validation for LOCA and PCMI Behaviour Using Measurements From the Halden Reactor Project

AU - Williamson, RL

AU - Pastore, G

AU - Spencer, BW

AU - Hales, JD

AU - Tverberg, T

PY - 2017/9/1

Y1 - 2017/9/1

N2 - BISON is a finite element-based nuclear fuel performance code that has been under development at Idaho National Laboratory (INL) since 2009. The code is applicable to both steady and transient fuel behavior and has been used to analyze a variety of fuel forms in 1D spherical, 1.5D and 2D axisymmetric, or 3D geometries. Efforts are underway to validate BISON for application to Light Water Reactor fuels using, to a large extent, experimental data from the Halden Reactor Project. Recent validation activities have included both Loss of Coolant Accident (LOCA) and Pellet Clad Mechanical Interaction (PCMI) experiments. Two such validation cases, the IFA-650.10 LOCA test and the IFA-629.4 power ramp test (PCMI), are summarized in this paper.

AB - BISON is a finite element-based nuclear fuel performance code that has been under development at Idaho National Laboratory (INL) since 2009. The code is applicable to both steady and transient fuel behavior and has been used to analyze a variety of fuel forms in 1D spherical, 1.5D and 2D axisymmetric, or 3D geometries. Efforts are underway to validate BISON for application to Light Water Reactor fuels using, to a large extent, experimental data from the Halden Reactor Project. Recent validation activities have included both Loss of Coolant Accident (LOCA) and Pellet Clad Mechanical Interaction (PCMI) experiments. Two such validation cases, the IFA-650.10 LOCA test and the IFA-629.4 power ramp test (PCMI), are summarized in this paper.

KW - BISON

KW - Halden Reactor Project

KW - validation

UR - https://www.osti.gov/biblio/1414448

M3 - Paper

T2 - EHPG 2017 - The 40th Enlarged Halden Program Group Meeting

Y2 - 24 September 2017 through 29 September 2017

ER -

BISON Validation for LOCA and PCMI Behaviour Using Measurements From the Halden Reactor Project

Abstract

Conference

Keywords

INL Publication Number

Access to Document

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