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  • HADA-2 (modified version of HADA) : A Fortran-IV program for the thermohydraulic design of an advanced pressurized light water reactor with a tight fuel rod lattice


The FORTRAN-IV program HADA, which computes the thermohydraulic parameters for Advanced Pressurised Light Water Reactors with a tight fuel rod lattice, has been modified to extend its applicability. The new version can be applied to homogeneous reactors using grid spacers with an arbitrary linear heat rating or an arbitrary core height. This version is also applicable to an axially heterogeneous reactor (multiple stacked core) which has been designed in JAERI and is not based on the modern PWR plant of German design. For users of the program, the present report describes the modifications and the input data in detail. Three sample runs demonstrate the usage of the program and the output. The solution algorithms are explained. The utility programs are described and an installation guide for the program system is listed.

Additional information

Authors: MORI T, Japan Atomic Energy Research Institute, Tokai-Mura, Naka-Gun, Ibaraki-Ken (JP);CIGARINI M, Mercedes Benz, Untertuerkheim, Stuttgart (DE);DALLE DONNE M, Kernforschungszentrum Karlsruhe, Institut fuer Neutronenphysik und Reaktortechnik (DE)
Bibliographic Reference: EUR 11395 EN (1990) 126 pp., MF, ECU 8
Availability: (2)
Record Number: 199010256 / Last updated on: 1994-12-01
Original language: en
Available languages: en