Published October 2009 | Version v1
Miscellaneous

Thermomechanical analysis of fuel rods during transitory events using the RAMONA and FETMA codes

  • 1. ININ, Departamento de Sistemas Nucleares, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

Description

In National Institute of Nuclear Research, the fuel management system (FMS) has been used by long time to simulate the BWR operation in stationary state, as well as during a transitory event. To evaluate the thermomechanical behavior of a fuel element was created and interface between the FMS codes and the fuel element thermo mechanical analysis (FETMA) code properly developed and implemented. In this work, the results of thermomechanical behavior of fuel rods that compose the hot channel during the simulation of a transitory event of a BWR are shown. The transitory events considered in this work are a load rejection and failure in controller of feed water, which are events more important that can to occur in a BWR. The results show that during the developed conditions by both transitory events some failure is not presented in fuel rods. Also, that the transitory event of load rejection is more claimant in security terms that of controller failure of feed water. (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.mx

Additional details

Additional titles

Original title (Spanish)
Analisis termomecanico de barras combustibles durante eventos transitorios usando los codigos RAMONA y FETMA

Publishing Information

Publisher
Sociedad Nuclear Mexicana
Imprint Place
Mexico D. F. (Mexico)
ISBN
978-607-95174-0-3
Imprint Pagination
10 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
41028840
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BWR TYPE REACTORS; FAILURES; FUEL MANAGEMENT; FUEL RODS; FUELS; HOT CHANNEL; REACTOR OPERATION; SECURITY; SIMULATION; WATER
Descriptors DEC
ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HYDROGEN COMPOUNDS; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; OPERATION; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS