Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects

NEA-1560 IFPE/BR3-HBFRHCP.

last modified: 16-JAN-2023 | catalog | new | search |

NEA-1560 IFPE/BR3-HBFRHCP.

IFPE/BR3-HBFRHCP, BR-3 High Burnup Fuel Rod Hot Cell Program

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

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1. NAME OF EXPERIMENT

IFPE/BR3-HBFRHCP

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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/BR3-HBFRHCP	NEA-1560/02	Arrived	16-JAN-2023

Machines used:

Package ID	Orig. computer	Test computer
NEA-1560/02	Many Computers

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3. DESCRIPTION

The United State Department of Energy sponsored the irradiation of five well-characterised PWR-type test rods to high burn-up in the BR-3 reactor located in Mol, Belgium. The principal aim of the tests was to demonstrate the feasibility of extending commercial fuel rod burn-up and thereby helping minimise radioactive waste disposal. The rods were of basic PWR radial dimensions and were fabricated by Westinghouse Corporation. The post-irradiation examinations (PIE) were carried out in the BR-2 hot cell facility at the Mol site.

The rods were of basic PWR radial dimensions. Goal peak burnups exceed 70 GWd/MTU.

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9. STATUS

Package ID	Status date	Status
NEA-1560/02	16-JAN-2023	Masterfiled restricted

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10. REFERENCES

NEA-1560/02, included references:

- M.G. Balfour et al.: BR-3 High Burnup Fuel Rod Hot Cell Program Volume 1:
Final Report WCAP-10238 Vol. 1 DOE/ET 34073-1 (Nov. 92)
- M.G. Balfour et al.: BR-3 High Burnup Fuel Rod Hot Cell Program Volume 2:
Data Summary WCAP-10238 Vol. 2 DOE/ET 34073-1 (Nov. 92)

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12. PROGRAMMING LANGUAGE(S) USED

No specified programming language

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15. AUTHORS

Westinghouse Electric Corporation

Nuclear Energy Systems

P.O. Box 355

Pittsburg, Pennsylvania 15230

USA

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16. MATERIAL AVAILABLE

NEA-1560/02

24i6.ltr,28i6.ltr,36i8.ltr,111i5.ltr FRAPCON-3 input decks for Westinghouse
PWR-type test rods irradiated in the BR-3 reactor,
input files for rods 111-I-5, 24-I-6, 28-I-6, and 36-I-8
Fuel rod characterisation
Non-destructive tests
QA Report
BR-3 test cases description

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17. CATEGORIES

Y. Integral Experiments Data, Databases, Benchmarks

Keywords: burnup, fuel behaviour, fuel rods, post-irradiation examination, pwr reactors.