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

NAME, COMPUTER, PROBLEM, STATUS, REFERENCES, LANGUAGE, AUTHOR, MATERIAL, CATEGORIES

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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.