Original Research Open Access Logo

Determination of the safety rods (SA, SB) for optimized power reactor 1000 using the Core simulator OPR1000

Son An Nguyen 1, *
Nguyen Trung Tran 1
  1. Đà Lạt University
Correspondence to: Son An Nguyen, Đà Lạt University. Email: pvphuc@vnuhcm.edu.vn.
Volume & Issue: Vol. 1 No. 6 (2017) | Page No.: 177-184 | DOI: 10.32508/stdjns.v1i6.627
Published: 2018-12-07

Online metrics


Statistics from the website

  • Abstract Views: 0
  • Galley Views: 0

Statistics from Dimensions

This article is published with open access by Viet Nam National University Ho Chi Minh City, Viet Nam. This article is distributed under the terms of the Creative Commons Attribution License (CC-BY 4.0) which permits any use, distribution, and reproduction in any medium, provided the original author(s) and the source are credited.

Abstract

In order to operate a nuclear power plant, ensuring safety is the most important factor. The function of safety rods are to shut down the reactor in case of emergency. The purpose of this paper to show the result of research and determine the value of safety rods SA, SB. Determination of the Boron concentration corresponding to each group of safety rods of OPR1000 nuclear reactor ensures the safely in the whole operation process. Experimental simulation is carried out in the system simulating core reactor OP1R1000 (CoSi OPR1000). The expermental result corresponds with the theoretic calculated result of Sa and Sb with 1500 pcm, 4000 pcm. The concentrations of Boron appropriately are 134 ppm and 284 ppm, respectively.

Comments