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Fracture Analysis of Vessels - Oak Ridge FAVOR, V04.1, Computer Code: User’s Guide (NUREG/CR-6855)On this page: Download complete document The following links on this page are to documents in Adobe Portable Document Format (PDF). See our Plugins, Viewers, and Other Tools page for more information. For successful viewing of PDF documents on our site please be sure to use the latest version of Adobe. Publication InformationManuscript Completed: October 2004 Prepared by Oak Ridge National Laboratory E. Focht, NRC Project Manager Prepared for AbstractThe current regulations to insure that nuclear reactor pressure vessels (RPVs) maintain structural
integrity when subjected to transients such as pressurized thermal shock (PTS) events were derived
from computational models developed in the early-to-mid 1980s. Since that time, advancements and
refinements in relevant technologies that impact RPV integrity assessment have led to an effort by the
NRC to re-evaluate its PTS regulations. Updated computational methodologies have evolved through
interactions between experts in the relevant disciplines of thermal hydraulics, probabilistic risk
assessment, materials embrittlement, fracture mechanics, and inspection (flaw characterization).
Contributors to the development of these methodologies include the NRC staff, their contractors, and
representatives from the nuclear industry. These updated methodologies have been integrated into the
Fracture Analysis of Vessels – Oak Ridge (FAVOR, v04.1) computer code developed for the NRC
by the Heavy Section Steel Technology (HSST) program at Oak Ridge National Laboratory (ORNL).
The FAVOR, v04.1, code represents the baseline NRC-selected applications tool for re-assessing the
current PTS regulations. Intended as a user’s guide to the computer system requirements, installation,
input data-deck preparation, and execution of the FAVOR, v04.1, deterministic and probabilistic
fracture mechanics code, this report is one of a series of software quality assurance documentation
deliverables being prepared according to the guidance provided in IEEE Std. 730.1-1995, IEEE Guide |
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