RAVEN Theory Manual
Creators
- 1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Description
RAVEN is a software framework able to perform parametric and stochastic analysis based on the response of complex system codes. The initial development was aimed at providing dynamic risk analysis capabilities to the thermohydraulic code RELAP-7, currently under development at Idaho National Laboratory (INL). Although the initial goal has been fully accomplished, RAVEN is now a multi-purpose stochastic and uncertainty quantification platform, capable of communicating with any system code. In fact, the provided Application Programming Interfaces (APIs) allow RAVEN to interact with any code as long as all the parameters that need to be perturbed are accessible by input files or via python interfaces. RAVEN is capable of investigating system response and explore input space using various sampling schemes such as Monte Carlo, grid, or Latin hypercube. However, RAVEN strength lies in its system feature discovery capabilities such as: constructing limit surfaces, separating regions of the input space leading to system failure, and using dynamic supervised learning techniques. The development of RAVEN started in 2012 when, within the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, the need to provide a modern risk evaluation framework arose. RAVEN's principal assignment is to provide the necessary software and algorithms in order to employ the concepts developed by the Risk Informed Safety Margin Characterization (RISMC) program. RISMC is one of the pathways defined within the Light Water Reactor Sustainability (LWRS) program. In the RISMC approach, the goal is not just to identify the frequency of an event potentially leading to a system failure, but the proximity (or lack thereof) to key safety-related events. Hence, the approach is interested in identifying and increasing the safety margins related to those events. A safety margin is a numerical value quantifying the probability that a safety metric (e.g. peak pressure in a pipe) is exceeded under certain conditions. Most of the capabilities, implemented having RELAP-7 as a principal focus, are easily deployable to other system codes. For this reason, several side activates have been employed (e.g. RELAP5-3D, any MOOSE-based App, etc.) or are currently ongoing for coupling RAVEN with several different software. The aim of this document is to provide a set of commented examples that can help the user to become familiar with the RAVEN code usage.
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 182 p.
- Report number
- INL/EXT--16-38178
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 47090310
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ALGORITHMS; COMPUTERIZED SIMULATION; COORDINATES; COUPLING; EQUIPMENT INTERFACES; EVALUATION; FAILURES; LEARNING; MANUALS; MATHEMATICAL SPACE; MONTE CARLO METHOD; PARAMETRIC ANALYSIS; PROGRAMMING; R CODES; RISK ASSESSMENT; SAFETY MARGINS; SAMPLING; STOCHASTIC PROCESSES; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; DOCUMENT TYPES; MATHEMATICAL LOGIC; REACTORS; SIMULATION; SPACE
Optional Information
- Contract/Grant/Project number
- AC07-05ID14517
- Funding organization
- USDOE Office of Nuclear Energy - NE (United States)
- Secondary number(s)
- OSTIID--1260312