last modified: 29-OCT-2004 | catalog | categories | new | search |

NEA-1729 IFPE/IFA-507-TF3-TF5

IFPE/IFA-507-TF3-TF5, Database For Transient Temperature Experiment Ifa-507

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1. NAME OF EXPERIMENT:  IFPE/IFA-507-TF3-TF5.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
IFPE/IFA-507-TF3-TF5 NEA-1729/01 Arrived 29-OCT-2004

Machines used:

Package ID Orig. computer Test computer
NEA-1729/01 Many Computers
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3. DESCRIPTION

At the Halden reactor a test at a power of ~15 MW was performed to study the transient temperature response of the two thermocoupled rods to  a rapid power increase. At the time of the experiment the burn-up of these rods was ~18 MWd/kgUO2. The experiment consisted of two parts, firstly to establish the steady state relationship between fuel temperature and shield position and secondly, a rapid withdrawal of the shield and continuous monitoring of the dynamic fuel temperature changes versus both shield position and time.
  
The approach adopted in the second part of the test was to lower the shield past the thermocouple tips (~10 cm below) to suppress the local rating at these locations and pull it rapidly upwards to uncover the portion of the fuel column containing the central oxide thermocouples.
  
The rods were subjected to a reactor SCRAM and temperatures monitored by the two thermocouples.
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4. METHODS

Data for the two rods equipped with thermocouples TF3 and TF5 were obtained from the following sources:
- ENIGMA code input files in electronic form
- Halden report HWR-120 by E Kolstad
- Halden Data Sheets compiled in HWR-273
  
The 6 rod cluster in IFA-507 was surrounded by a moveable silver shield encased in stainless steel which was capable of reducing the power to about 50% of the full power rating. A schematic diagram of the assembly with the axial power profile is shown in the accompanying figure. The rods in the cluster were BWR design with Zr-2 cladding two of which contained centreline thermocouples designated TF3 and TF5.
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9. STATUS
Package ID Status date Status
NEA-1729/01 29-OCT-2004 Arrived at NEADB
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10. REFERENCES
NEA-1729/01, included references:
- E Kolstad:
A Study of the Thermal Behaviour of LWR Fuel Designs under Transient Power
Conditions, HWR-120, April 1984
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

Institutt for Energiteknikk
OECD Halden Reactor Project
P.O. Box 173
N-1751 HALDEN
NORWAY
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16. MATERIAL AVAILABLE
NEA-1729/01
Summary IFA 507.doc  Description of the experiment
IFA-507-CHAR.doc Pre-characterization data for pellets, cladding and each fuel
rod
TF3-SS  Base irradiation histories for rod containing thermocouple TF3
TF5-SS  Base irradiation histories for rod containing thermocouple TF5
TF3-TRN Power history for rod containing TF3 during shield lift transient
TF5-TRN Power history for rod containing TF5 during shield lift transient
507-TP  Steady state temperature dependence on local power from TF3 & TF5
507-T3  Digitized data for TF3 as a function of time during  shield lift
transient
507-T5  Digitized data for TF5 as a function of time during shield lift
transient
IFA507-TF3-ss-t.xls  Response of TF3 assuming steady state relation between
power and temperature and Response of TF3 during transient in EXCEL version with

graph
IFA507-TF5-ss-t.xls  Response of TF5 assuming steady state relation between
power and temperature and Response of TF5 during transient in EXCEL version with

graph
IFA507-TF3-TF5-linpow.xls  Steady state relationship between thermocouples and
power for IFA-507 TF3 and TF5
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: fuel behaviour, steady-state conditions, temperature, thermal power plants, thermocouples, transients.