Analysis of Thermal-Hydraulic Fluctuations in Trillo NPP With CTF/PARCS v. 2.7 Coupled Code-Reference-Cited by-同舟云学术

Analysis of Thermal-Hydraulic Fluctuations in Trillo NPP With CTF/PARCS v. 2.7 Coupled Code

Published:2016-02-29 Issue:2 Volume:2 Page:
ISSN:2332-8983
Container-title:Journal of Nuclear Engineering and Radiation Science
language:en
Short-container-title:

Author:

Abarca A.¹,Miró R.¹,Verdú G.¹,Bermejo J. A.²

Affiliation:

1. Institute for Industrial, Radiophysical and Environmental Safety (ISIRYM), Universitat Politècnica de València, Camí de Vera s/n, 46021 València, Spain e-mail:

2. Iberdrola Ingeniería y Construcción S.A.U, Av. Manoteras, 20. Edificio C, 28050 Madrid, Spain e-mail:

Abstract

The low-frequency noises are fluctuations in the neutron flux density, in the low-frequency range up to 4 Hz, which generate noise in the neutron instrumentation and could affect the limitation and protection system of the reactor core. Some European pressurized water reactors (PWRs) experienced the effect of low-frequency noise, opening a new research line for the verification of the neutron-kinetics/thermal-hydraulic coupled codes. A CTF/PARCS v. 2.7 simulation study to verify whether periodical fluctuations in the core inlet temperature could activate the core protection system has been done, obtaining the frequency spectrum of the power oscillation amplitudes.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Link

http://asmedigitalcollection.asme.org/nuclearengineering/article-pdf/doi/10.1115/1.4031660/6067668/ners_2_2_021023.pdf

Reference5 articles.

1. Grondey, G., Harms, R., Kumpf, H., and Winderl, G., 1992, “Low Frequency Noise in a PWR and Its Influence on the Normal Operational Characteristics of the Plant,” Nuclear Energy Agency of the OECD: Proceedings of a Specialists’ Meeting on In-core Instrumentation and Reactor Core Assessment, Pittsburg, PA, Oct. 1–4 1991, pp. 183–191.

2. Abarca, A., Miró, R., Barrachina, T., and Verdú, G., 2011, “A Procedure for Coupled Thermal-Hydraulic Subchannel and Neutronic Codes Using COBRA-TF and PARCS,” International Nuclear Atlantic Conference—INAC, Belo Horizonte, MG, Brazil, Oct. 24–28.

3. Cronin, J. T., Smith, K. S., and Planck, D. M. V., 1995, “SIMULATE-3. Advanced Three-Dimensional Two-Group Reactor Analysis Code,” Studsvik, Tech. Rep. SOA-95/18.

4. PARCS v.2.7 U.S. NRC Core Neutronics Simulator: User Manual,2006

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