RELAP-7: Next-Generation Nuclear Safety Code

INL Software; Richard Martineau; David Andrs; Ray Berry; Hongbin Zhang; Ling Zou; Haihua Zhao; John Peterson; Cody Permann; Derek Gaston; Frederick Gleicher; Javier Ortensi; Joshua Hansel; Andrew Franklin; Robert Carlson; Lise Charlot; Russel Johns; Marc Delchini

RELAP-7: Next-Generation Nuclear Safety Code

INL Software (Photographer), Richard Martineau (Developer), David Andrs (Developer), Ray Berry (Developer), Hongbin Zhang (Developer), Ling Zou (Developer), Haihua Zhao (Developer), John Peterson (Developer), Cody Permann (Developer), Derek Gaston (Developer), Frederick Gleicher (Developer), Javier Ortensi (Developer), Joshua Hansel (Developer), Andrew Franklin (Developer), Robert Carlson (Developer), Lise Charlot (Developer), Russel Johns (Developer), Marc Delchini (Developer)

Research output: Non-textual form › Software

Abstract

A next generation nuclear systems safety code, RELAP-7 takes advantage of advances in computer architecture, software design, numerical methods, and physical models for use in the Risk Informed Safety Margin Characterization (RISMC) methodology and in nuclear power plant (NPP) safety analysis. RELAP-7 is a more capable than its predecessors in the RELAP family due to better flow models, improved numerical approximations, the ability to handle long duration events like full life cycle fuel evaluations, and easy coupling to other simulation code.

This software is a controlled nuclear code, subject to a special release process due to its sensitive nature. To request access, please visit the Nuclear Computational Resource Center and create an account.

Original language	American English
State	Published - 2015

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https://inlsoftware.inl.gov/product/relap-7

Cite this

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title = "RELAP-7: Next-Generation Nuclear Safety Code",

abstract = "A next generation nuclear systems safety code, RELAP-7 takes advantage of advances in computer architecture, software design, numerical methods, and physical models for use in the Risk Informed Safety Margin Characterization (RISMC) methodology and in nuclear power plant (NPP) safety analysis. RELAP-7 is a more capable than its predecessors in the RELAP family due to better flow models, improved numerical approximations, the ability to handle long duration events like full life cycle fuel evaluations, and easy coupling to other simulation code.This software is a controlled nuclear code, subject to a special release process due to its sensitive nature. To request access, please visit the Nuclear Computational Resource Center and create an account.",

author = "{INL Software} and Richard Martineau and David Andrs and Ray Berry and Hongbin Zhang and Ling Zou and Haihua Zhao and John Peterson and Cody Permann and Derek Gaston and Frederick Gleicher and Javier Ortensi and Joshua Hansel and Andrew Franklin and Robert Carlson and Lise Charlot and Russel Johns and Marc Delchini",

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A2 - Zhao, Haihua

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A2 - Permann, Cody

A2 - Gaston, Derek

A2 - Gleicher, Frederick

A2 - Ortensi, Javier

A2 - Hansel, Joshua

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AB - A next generation nuclear systems safety code, RELAP-7 takes advantage of advances in computer architecture, software design, numerical methods, and physical models for use in the Risk Informed Safety Margin Characterization (RISMC) methodology and in nuclear power plant (NPP) safety analysis. RELAP-7 is a more capable than its predecessors in the RELAP family due to better flow models, improved numerical approximations, the ability to handle long duration events like full life cycle fuel evaluations, and easy coupling to other simulation code.This software is a controlled nuclear code, subject to a special release process due to its sensitive nature. To request access, please visit the Nuclear Computational Resource Center and create an account.

M3 - Software

ER -

RELAP-7: Next-Generation Nuclear Safety Code

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