Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
NEA-1488 IFPE/IFA-432.
last modified: 29-JAN-1996 | catalog | new | search |

NEA-1488 IFPE/IFA-432.

IFPE/IFA-432, Fission Gas Release, Mechanical Interaction BWR Fuel Rods, Halden

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1. NAME OF EXPERIMENT

IFPE/IFA-432

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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/IFA-432 NEA-1488/02 Arrived 29-JAN-1996

Machines used:

Package ID Orig. computer Test computer
NEA-1488/02 Many Computers
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3. DESCRIPTION

This package contains data from experiments that have been performed at the IFE/OECD Halden Reactor Project, available for use in fuel performance studies. It covers experiments on thermal performance, fission product release, clad properties and pellet clad mechanical interaction. It includes also experimental data relevant to high burn-up behaviour.

 

IFA-432: Measurements of fuel temperature response, fission gas release and mechanical interaction on BWR-type fuel rods up to high burn-ups. The assembly featured several variations in rod design parameters, including fuel type, fuel/cladding gap size, fill gas composition (He and Xe) and fuel stability. It contained 6 BWR-type fuel rods with fuel centre thermocouples at two horizontal planes, rods were also equipped with pressure transducers and cladding extensometers. Only data from 6 rods are compiled here.

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9. STATUS
Package ID Status date Status
NEA-1488/02 29-JAN-1996 Masterfiled restricted
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10. REFERENCES
NEA-1488/02, included references:
- D.D. Lanning and E.R. Bradley: Retained Fission Gas Measurements from IFA-432
Rods 1 and 6 HPR-320/5 (May 1984)
- D.D.Lanning and E.R. Bradley: Final Irradiation and Postirradiation Data from
the NRC/PNL Instrumented Assemby IFA-432, HPR-329/7
- K. Ranta-Puska, S. Kelppe: Testing Steady State Fission Gas Release and
Thermal Behaviour Model Predictions with IFA-505 and IFA-432 Data, HPR-336/12
(May 1988)
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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: J.A. Turnbull

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16. MATERIAL AVAILABLE
NEA-1488/02
ROD1,2,3,5 and 6 Condensed irradiation histories for rods 1, 2, 3, 5 and 6
TF*R Data for lower thermocouples of IFA-432 as a function of power for several
levels of burn-up throughout the irradiation
TF*.20 & TF*.30 Data at constant power for lower thermocouples of IFA-432 as a
function of burn-up.
SCRAM.AUG, SCRAM.JAN Data logged at 500 msec intervals from thermocouples TF1,
TF4 and TF8 immediately following reactor scrams in August 1979 and January
1980.
EC* Rod elongation at intervals throughout the irradiation.
*.for Simplified power history programs
Data files
Readme files and descriptions
QA report 432.pdf QA report
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: BWR reactors, burnup, experimental data, fission products, fuel elements, fuel pellets, fuel rods, fuel-cladding interaction, fuel-coolant interactions, helium, xenon.