RAVEN (Reactor Analysis and Virtual control ENviroment) [1, 2] is a software framework that acts as the control logic driver for the Thermo-Hydraylic code RELAP-7, a newly developed software at Idaho National Laboratory. The aim of this paper is to provide an overview of the software structure and its utilization in conjunction with RELAP-7/MOOSE [3, 4]. RAVEN is a multi-purpose Probabilistic Risk Assement (PRA) code that allows dispatching different functionalities. It is designed to derive and actuate the control logic required to simulate the plant control system and operator actions (guided procedures) and to performboth Monte-Carlo sampling ofrandom distributed events and dynamic event tree based analysis [5]. In order to assist the user in the input/output handling, a Graphical User Interface (GUI) and a post-processing data mining module, based on dimensionality and cardinality reduction [6], are available. This paper wants to point up the link between the software layout and the
RAVEN (Reactor Analysis and Virtual control ENviroment) [1, 2] is a software framework that acts as the control logic driver for the Thermo-Hydraylic code RELAP-7, a newly developed software at Idaho National Laboratory. The aim of this paper is to provide an overview of the software structure and its utilization in conjunction with RELAP-7/MOOSE [3, 4]. RAVEN is a multi-purpose Probabilistic Risk Assement (PRA) code that allows dispatching different functionalities. It is designed to derive and actuate the control logic required to simulate the plant control system and operator actions (guided procedures) and to performboth Monte-Carlo sampling ofrandom distributed events and dynamic event tree based analysis [5]. In order to assist the user in the input/output handling, a Graphical User Interface (GUI) and a post-processing data mining module, based on dimensionality and cardinality reduction [6], are available. This paper wants to point up the link between the software layout and the mathematical framework from which its structure is derived. In order to show some capabilities, a demo of a Station Black Out (SBO) analysis of a simplified Pressurized Water Reactor (PWR) model is reported.
Performing Probabilist Risk Assessment Through RAVEN / Alfonsi, Andrea; C., Rabiti; D., Mandelli; J., Cogliati; R., Kinoshita. - STAMPA. - (2013), pp. ...-.... (Intervento presentato al convegno American Nuclear Society 2013 Annual Meeting "Next Generation Nuclear Energy: Prospects and Challenges" tenutosi a Atlanta, USA nel 16-20 Giugno 2013).
Performing Probabilist Risk Assessment Through RAVEN
ALFONSI, ANDREA;
2013
Abstract
RAVEN (Reactor Analysis and Virtual control ENviroment) [1, 2] is a software framework that acts as the control logic driver for the Thermo-Hydraylic code RELAP-7, a newly developed software at Idaho National Laboratory. The aim of this paper is to provide an overview of the software structure and its utilization in conjunction with RELAP-7/MOOSE [3, 4]. RAVEN is a multi-purpose Probabilistic Risk Assement (PRA) code that allows dispatching different functionalities. It is designed to derive and actuate the control logic required to simulate the plant control system and operator actions (guided procedures) and to performboth Monte-Carlo sampling ofrandom distributed events and dynamic event tree based analysis [5]. In order to assist the user in the input/output handling, a Graphical User Interface (GUI) and a post-processing data mining module, based on dimensionality and cardinality reduction [6], are available. This paper wants to point up the link between the software layout and theI documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
