A comparative study of boron transport models in NRC thermal-hydraulic code TRACE

Authors

  • N Olmo-Juan Universidad Politécnica de Valencia
  • T Barrachina Universidad Politécnica de Valencia
  • R Miro Universidad Politécnica de Valencia
  • Claubia Lima Universidad Politécnica de Valencia
  • Claubia Pereira Universidade Federal de Minas Gerais

DOI:

https://doi.org/10.15392/bjrs.v7i2B.767

Keywords:

boron transport, TRACE, high order schemes

Abstract

Recently, the interest in the study of various types of transients involving changes in the boron concentration inside the reactor, has led to an increase in the interest of developing and studying new models and tools that allow a correct study of boron transport. Therefore, a significant variety of different boron transport models and spatial difference schemes are available in the thermal-hydraulic codes. According to this interest, in this work it will be compared the results obtained using the different boron transport models implemented in the NRC thermal-hydraulic code TRACE. To do this, a set of models has been created using the different options and configurations that could have influence in boron transport. These models allow us to reproduce a simple event of filling or emptying the boron concentration in a long pipe. Moreover, with the aim to compare the differences obtained when one-dimensional or three-dimensional components are chosen, it has modeled many different cases using only pipe components or a mix of pipe and vessel components. In addition, the influence of the void fraction in the boron transport has been studied and compared under close conditions to a BWR commercial model. A final collection of the different cases and boron transport models are compared between them and those corresponding to the analytical solution provided by the Burgers equation. From this comparison, important conclusions are drawn that will be the basis of modeling the boron transport in TRACE adequately.

Downloads

Download data is not yet available.

References

BARRACHINA T., SOLER A., OLMO-JUAN N., MIRÓ R., VERDÚ G. J., CONCEJAL A. Development of a high order boron transport scheme, In: JOINT INTERNATIONAL CONFER-ENCE ON MATHEMATICS AND COMPUTATION (M&C), SUPERCOMPUTING IN NUCLEAR APPLICATIONS (SNA) AND THE MONTE CARLO (MC) METHOD, 2015, Nashville,TN, USA. CD-ROM, American Nuclear Society, LaGrange Park, IL (2015)

OLMO-JUAN N., BARRACHINA T.M., MIRÓ R., QUEROL A., VERDÚ G.J., PEREIRA C. A comparative study of boron transport in thermal-hydraulic codes TRACE vs TRAC-BF1 and TRACE vs RELAP5, In: 17TH INTERNATIONAL TOPICAL MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS, 2017, Xi’an, China.

U. S. Nuclear Regulatory Commission, TRACE V5.0 – Theory Manual, Washington, DC 20555 (2012).

Downloads

Published

2019-07-09

Issue

Section

XX Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XX ENFIR)

How to Cite

A comparative study of boron transport models in NRC thermal-hydraulic code TRACE. Brazilian Journal of Radiation Sciences, Rio de Janeiro, Brazil, v. 7, n. 2B (Suppl.), 2019. DOI: 10.15392/bjrs.v7i2B.767. Disponível em: https://www.bjrs.org.br/revista/index.php/REVISTA/article/view/767.. Acesso em: 8 may. 2024.

Similar Articles

1-10 of 406

You may also start an advanced similarity search for this article.

Most read articles by the same author(s)

1 2 > >>