Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
NEA-1599 IFPE/FUMEX-1.
last modified: 16-JAN-2023 | catalog | new | search |

NEA-1599 IFPE/FUMEX-1.

IFPE/FUMEX-1, Data from OECD Halden Reactor Project for FUMEX-1 (Fuel Modelling at Extended Burnup)

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1. NAME OF EXPERIMENT

IFPE/FUMEX-1

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.

Program name Package id Status Status date
IFPE/FUMEX-1 NEA-1599/02 Arrived 16-JAN-2023

Machines used:

Package ID Orig. computer Test computer
NEA-1599/02 Many Computers
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3. DESCRIPTION

This set contains the experimental data from the OECD Halden Reactor Project made available for the FUMEX-I exercise (Fuel Modelling at Extended Burnup) carried out under the auspices of the IAEA.

 

The six cases are:

 

FUMEX 1:This data set represents the irradiation of production line PWR type fuel under benign conditions. Temperatures remained low but increased slightly with burnup.

FUMEX 2:This was a small diameter rod designed to achieve rapid accumulation of burnup. Temperatures were estimated to remain low. The internal pin pressure was measured in-pile and an assessment of FGR was also provided by PIE.

FUMEX 3: This case consisted of 3 short rods equipped with centreline thermocouples each with a different gap and fill gas composition. After steady state irradiation to ~30 MW.d/kg UO2, they were given a severe increase in power (power ramp).

FUMEX 4: Two rods filled with 3 bar He and 1 bar He/Xe mixture were irradiated to ~33 MW.d/kg UO2. Both rods experienced a period of increased power part way through the irradiation.

FUMEX 5: The test case comprised a single rod base irradiated at low power to 16 MW.d/kg UO2 with a power ramp and a hold period at the end of life. The main purpose of this case was to assess pellet clad mechanical interaction (PCMI) and fission gas release (FGR) under ramp conditions.

FUMEX 6: Two rods were base irradiated at low power. The rods were refabricated to include pressure transducers. Rod internal pressure was monitored during power ramps, one fast, one slow.

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9. STATUS
Package ID Status date Status
NEA-1599/02 16-JAN-2023 Masterfiled restricted
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10. REFERENCES
NEA-1599/02, included references:
- Dr. W. Wiesenack:
Further Specifications of FUMEX input data OECD Halden Reactor Project, Notes
to recipients of FUMEX cases dated Sept.2, 1993 and Jan.12, 1994
- Fuel Modelling at Extended Burnup, Report of the Co-ordinated Research
Programme on Fuel Modelling at Extended Burnup - FUMEX (1993-1996),
IAEA-TECDOC-998 (January 1998)
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. AUTHORS

OECD Halden Reactor Project

Institutt for Energiteknikk

P.O. Box 173

N-1751 HALDEN

Norway

 

Compilation: R. J. White

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16. MATERIAL AVAILABLE
NEA-1599/02
*.f90                       Fortran programs for history generation
*.DAT                      Raw fumex histories
*.h1                        Supplementary information
*.o1                        New power histories
*.o2                        Simplified power histories for graphical checks
*.JNB files
FUMEX.doc                   Fuel rod specifications
fumex-his.doc               FUMEX power histories
QA Report for fumex.doc     QA report
Summary.doc                 Summay report
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: burnup, cladding, creep, fission gas release, fuel behaviour, post-irradiation examination, power ramp, pwr reactors.