The RETRAN-3D Code; Pressurized Water Reactor Multidimensional Neutron Kinetics Applications

• Published in: Nuclear technology Vol. 122; no. 2; pp. 132 - 145
• Main Authors: Gose, Garry C., Shatford, John G., Agee, Lance J.
• Format: Journal Article
• Language: English
• Published: La Grange Park, IL Taylor & Francis 01.05.1998; American Nuclear Society
• Subjects: Applied sciences; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Installations for energy generation and conversion: thermal and electrical energy; Three dimensional model; Cooling system; Computation code; Thermohydraulics; Kinetics; Pressurized water reactor; Nuclear reactor
• ISSN: 0029-5450; 1943-7471
• DOI: 10.13182/NT98-A2857

A RETRAN-03 computer code version has been developed to analyze reactor transients requiring three-dimensional reactor core neutronics models. The new code will enable the user to couple a complex RETRAN nuclear steam supply system model to a detailed multidimensional neutronics core model. The neutronics model is based on a three-dimensional nodal model using the analytic nodal method that allows a detailed three-dimensional representation of the core but requires less computational effort than conventional fine-mesh finite difference methods. The model uses a full two-group diffusion equation implementation coupled to six delayed neutron groups. Two representative analyses were used as evaluation cases. The work involved the first use of the RETRAN-03 advanced system analysis code using three-dimensional neutronics methods. The purpose of these studies was to gain experience in RETRAN-3D modeling methods and to compare the results with previous calculations as part of a code verification effort. The work has led to a new capability for the RETRAN-03 code, enabling the user to examine the core behavior in more detail than in previous versions and to study transients that involve nonsymmetric core behavior.