Published June 2020 | Version v1
Report

Qualification of FRAPCON/FRAPTRAN for LOCA fuel behaviour modelling and safety evaluation

  • 1. Tractebel (ENGIE), Boulevard Simon Bolivar 34–36, 1000, Brussels (Belgium)

Description

As part of the Tractebel contribution to the IAEA FUMAC project, Tractebel has used the updated FRAPTRAN-TE-1.5 code for simulation of selected Halden LOCA tests IFA-650.9 and IFA-650.10, together with the improvement in the thermal hydraulic modelling by using the imposed thermal hydraulic boundary conditions from SOCRAT calculations and in the thermal boundary conditions (axial power profile, plenum temperature). In particular, the impacts of the model improvements such as the Quantum Technologies' axial relocation model and errors corrections in the adapted FRAPTRAN-TE-1.5 version on the calculation results were identified and discussed. In addition, the statistical uncertainty and sensitivity analysis has been performed on the FRAPTRAN-TE-1.5 modelling of the selected Halden LOCA test IFA-650.10, which helped the identification of significant input parameters for LOCA fuel Behaviour modelling. The final objective is to apply the qualified fuel rod transient analysis codes FRAPCON/FRAPTRAN to develop an efficient methodology for assessing the performance and quantifying the margins for advanced technology fuel (ATF) designs under design basis accident conditions (in particular LOCAs). (author)

Part of:
Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions. Proceedings of a Technical Meeting

Additional details

Publishing Information

ISBN
978-92-0-108020-2
Imprint Title
Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions. Proceedings of a Technical Meeting
Imprint Pagination
222 p.
Journal Page Range
p. 29-39
ISSN
1011-4289
Report number
IAEA-TECDOC--1913

Conference

Title
Technical Meeting on Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions
Dates
13-16 May 2019
Place
Shenzhen (China)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
51060443
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCIDENT-TOLERANT NUCLEAR FUELS; BOUNDARY CONDITIONS; DESIGN-BASIS ACCIDENTS; FUEL RODS; IAEA; LOSS OF COOLANT; PERFORMANCE; SAFETY ANALYSIS; SENSITIVITY ANALYSIS; SIMULATION; THERMAL HYDRAULICS
Descriptors DEC
ACCIDENTS; ENERGY SOURCES; FLUID MECHANICS; FUEL ELEMENTS; FUELS; HYDRAULICS; INTERNATIONAL ORGANIZATIONS; MATERIALS; MECHANICS; NUCLEAR FUELS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR MATERIALS

Optional Information

Notes
18 refs., 2 figs., 3 tabs.