Document: NUREG-0800
Document ID: 643ab154-682e-480f-a57b-a5fd7390a34e
Document Type: srp
Title: REVIEW OF TRANSIENT AND ACCIDENT ANALYSIS METHODS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0535/ML053550265.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0.2
CFR Part: 
CFR Title: 

Content:
). Frozen The condition whereby the analytical tool(s) and associated facility input decks remain unchanged (and under configuration control) throughout a safety analysis thereby ensuring traceability of, and consistency in, the final results. General Design Design criteria described in Appendix A to 10 CFR Part 50. Criteria Homogeneous An analytical model for two-phase flow that assumes (1) both phases Equilibrium Model move at the same velocity, (2) the fluid is in thermal equilibrium, and (3) the flow is isentropic and steady. Integral Effects An experiment in which the primary focus is on the interactions Test between parameters and processes. 15.0.2-19 Initial Issuance - December 2005 Model (without “evaluation” modifier) - Equation or set of equations that represents a particular physical phenomenon within a calculational device. Peak Cladding The maximum fuel element cladding temperature. Temperature Phase State of matter involved in transport process, usually liquid or gas. Phenomena May refer to a table, or to a process depending on context of use. The Identification process relates to determining the relative importance of phenomena and Ranking Table (and/or physical processes) to the behavior of a nuclear power plant following the initiation of an accident or other transient. A PIRT table is a listing of the results of application of the process. Request for A documented request, usually in the form of questions, sent by the additional NRC to the submitter to obtain more information on areas under review. information Roadmap A document used to facilitate navigation through a larger and complex set of documentation. Scaling The process in which the results from a subscale facility (relative to a nuclear power plant) and/or the modeling features of a calculational device are evaluated to determine the degree to which they represent a nuclear power plant. Scaling Distortions Errors introduced into the data as a result of scaling the experimental