Published July 2018 | Version v1
Miscellaneous Restricted

FITX: a fast burn-up scheme based on the fitting of one-group cross-sections

  • 1. Budapest University of Technology and Economics, Institute of Nuclear Techniques, 1111 Budapest (Hungary)

Description

Due to the high computational cost of detailed burn-up calculations, most scenario codes use burn-up tables or parametrized few group cross-sections to calculate fuel depletion in the reactors. As a special parametrization approach, a fast burn-up scheme called FITXS was developed at the BME Institute of Nuclear Techniques (BME NTI), which is based on the fitting of one-group cross-sections as polynomial functions of the detailed fuel composition. The FITXS scheme was used to develop burn-up models for the Generation IV Gas-cooled Fast Reactor (GFR), Lead-cooled Fast Reactor (LFR) and Sodium-cooled Fast Reactor (SFR), as well as MOX fuel assemblies of the Generation III European Pressurized Reactor (EPR) and VVER-1200. This document is composed of an introduction and the slides of the presentation.

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Part of:
3. technical workshop on fuel cycle simulation - Abstracts and slides

Additional details

Publishing Information

Imprint Title
3. technical workshop on fuel cycle simulation - Abstracts and slides
Imprint Pagination
611 p.
Journal Page Range
p. 196-216
Report number
INIS-FR--18-1372

Conference

Title
3. technical workshop on fuel cycle simulation
Dates
9-11 Jul 2018
Place
Paris (France)

Optional Information

Notes
2 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses