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DOE OSTI · 1358197

RELAP-7 Code Assessment Plan and Requirement Traceability Matrix

Yoo, Junsoo·Choi, Yong-joon·Smith, Curtis L.
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Abstract

The RELAP-7, a safety analysis code for nuclear reactor system, is under development at Idaho National Laboratory (INL). Overall, the code development is directed towards leveraging the advancements in computer science technology, numerical solution methods and physical models over the last decades. Recently, INL has also been putting an effort to establish the code assessment plan, which aims to ensure an improved final product quality through the RELAP-7 development process. The ultimate goal of this plan is to propose a suitable way to systematically assess the wide range of software requirements for RELAP-7, including the software design, user interface, and technical requirements, etc. To this end, we first survey the literature (i.e., international/domestic reports, research articles) addressing the desirable features generally required for advanced nuclear system safety analysis codes. In addition, the V&V (verification and validation) efforts as well as the legacy issues of several recently-developed codes (e.g., RELAP5-3D, TRACE V5.0) are investigated. Lastly, this paper outlines the Requirement Traceability Matrix (RTM) for RELAP-7 which can be used to systematically evaluate and identify the code development process and its present capability.

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BibTeXRIS

Yoo, Junsoo, Choi, Yong-joon, Smith, Curtis L.. 2016-10-01. RELAP-7 Code Assessment Plan and Requirement Traceability Matrix. https://www.osti.gov/biblio/1358197

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