Depending on the specific event scenario and on the purpose of the analysis, it might be required the availability of calculation methods that are not implemented in the standard system thermal hydraulic codes. This may imply the use of a dedicated fuel rod thermo-mechanical computer code. This paper provides an outline of the methodology for the analysis of the 2A LB-LOCA accident in Atucha-2 NPP and describes the procedure adopted for the use of the fuel rod thermo-mechanical code. The methodology implies the application of best estimate thermal-hydraulic, neutron physics and fuel pin performance computer codes, with the objective to verify the compliance with the specific acceptance criteria. The fuel pin performance code is applied with the main objective to evaluate the extent of cladding failures during the transient. The procedure consists of a deterministic calculation by the fuel performance code of each individual fuel rod during its lifetime and in the subsequent LB-LOCA transient calculations. The boundary and initial conditions (e.g. pin power axial profiles) are provided by core physics and three dimensional neutron kinetic coupled thermal-hydraulic system codes (RELAP5-3D©) calculations. The procedure is completed by the sensitivity calculations and the application of the probabilistic method, with the aim of a better understanding of the uncertainties involved and their technological consequences on the behavior of the fuel rods, not addressed in the current paper.
Skip Nav Destination
18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4929-3
PROCEEDINGS PAPER
A Procedure to Address the Fuel Rod Failures During LB-LOCA Transient in Atucha-2 NPP Available to Purchase
Martina Adorni,
Martina Adorni
University of Pisa, Pisa, Italy
Search for other works by this author on:
Alessandro Del Nevo,
Alessandro Del Nevo
University of Pisa, Pisa, Italy
Search for other works by this author on:
Francesco D’Auria,
Francesco D’Auria
University of Pisa, Pisa, Italy
Search for other works by this author on:
Oscar Mazzantini
Oscar Mazzantini
Nucleoele´ctrica Argentina S.A., Lima, Argentina
Search for other works by this author on:
Martina Adorni
University of Pisa, Pisa, Italy
Alessandro Del Nevo
University of Pisa, Pisa, Italy
Francesco D’Auria
University of Pisa, Pisa, Italy
Oscar Mazzantini
Nucleoele´ctrica Argentina S.A., Lima, Argentina
Paper No:
ICONE18-30329, pp. 367-376; 10 pages
Published Online:
April 8, 2011
Citation
Adorni, M, Del Nevo, A, D’Auria, F, & Mazzantini, O. "A Procedure to Address the Fuel Rod Failures During LB-LOCA Transient in Atucha-2 NPP." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 1. Xi’an, China. May 17–21, 2010. pp. 367-376. ASME. https://doi.org/10.1115/ICONE18-30329
Download citation file:
10
Views
Related Proceedings Papers
Related Articles
COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments
ASME J of Nuclear Rad Sci (July,2016)
Pellet-Cladding Interaction of LMFBR Fuel Elements at Unsteady State: An Introduction to Computer Code ISUNE-5
J. Eng. Power (October,1981)
Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria
ASME J of Nuclear Rad Sci (April,2017)
Related Chapters
Effect of Chromium Content on the On-Cooling Phase Transformations and Induced Prior-β Zr Mechanical Hardening and Failure Mode (in Relation to Enhanced Accident-Tolerant Fuel Chromium-Coated Zirconium-Based Cladding Behavior upon and after High-Temperature Transients)
Zirconium in the Nuclear Industry: 20th International Symposium
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Long.Term Reactivity Change and Control: On.Power Refuelling
Fundamentals of CANDU Reactor Physics