Estimate of coolant flow in assemblies of a natural circulation BWR applying and equivalent electric model
Creators
- 1. UNAM, DEPFI, Laboratorio de Analisis de Ingenieria de Reactores Nucleares, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)
- 2. Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Mexico D. F. (Mexico)
Description
The present work exposes the design and implementation of an advanced controller that it allows to estimate the coolant flow in fuel assemblies of a natural circulation BWR in real time. the complete development of this study is part of a doctoral project in course. In this work the construction of optimal controller is shown that allows to estimate the coolant flows in reactor and its operation applied to an equivalent electric model to natural circulation ESBWR. The controller design that allows the completely automatic starter of natural circulation reactor, required of a variables estimator not meter directly of nuclear power plant and use of local distributions estimates of coolant flow, (this controller type at the moment is utilized in the A BWR and several BWR in operation in Japan). The construction of estimator controller is mathematically based in the theory referring to Kalman filter, whose algorithm provides an advanced control of system. To prove the estimator operation was developed a simplified model that reproduces the basic dynamic of coolant flowing in the ESBWR, a practice way and very interesting of representing this phenomenon is by means the use of an equivalent electric model, which was developed starting from analogies that there is among the relation that keep the pressure differences with the mass flow and differences of electric potential with electric current. A detailed analysis of equivalence among models will be presented in a later article. (Author)
Availability note (English)
Available from the Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion, 52045 Ocoyoacac, Estado de Mexico (MX), e-mail: javier.ortega@inin.gob.mx; claudio.fernandez@inin.gob.mxAdditional details
Additional titles
- Original title (Spanish)
- Estimacion del flujo de refrigerante en los ensambles de un BWR de circulacion natural aplicando un modelo electrico equivalente
Publishing Information
- Publisher
- Sociedad Nuclear Mexicana
- Imprint Place
- Mexico D. F. (Mexico)
- ISBN
- 978-607-95174-0-3
- Imprint Pagination
- 16 p.
Conference
- Title
- trends of the nuclear energy
- Original Conference Title
- 20. Congreso Anual de la SNM : perspectivas y retos de la energia nuclear
- Acronym
- 20. SNM Annual Congress
- Dates
- 5-8 Jul 2009
- Place
- Puerto Vallarta, Jal. (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 41036613
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ALGORITHMS; BWR TYPE REACTORS; CONTROL; COOLANTS; DESIGN; DISTRIBUTION; ELECTRIC CURRENTS; ELECTRIC POTENTIAL; FUEL ASSEMBLIES; IMPLEMENTATION; MASS; NATURAL CONVECTION; OPERATION
- Descriptors DEC
- CONVECTION; CURRENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; MASS TRANSFER; MATHEMATICAL LOGIC; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS