Abstract

Nuclear power with strengthened safety regulations continues to be used as an important resource in the world for managing atmospheric greenhouse gases and associated climate change. This study examined the environmentally benign separation of zirconium tetrachloride (ZrCl4) and hafnium tetrachloride (HfCl4) for nuclear power reactor applications through extractive distillation using a NaCl-KCl molten salt mixture. The vapor–liquid equilibrium behavior of ZrCl4 and HfCl4 over the molten salt system was correlated with Raoult’s law. The molten salt-based extractive distillation column was designed optimally using a rigorous commercial simulator for the feasible separation of ZrCl4 and HfCl4. The molten salt-based extractive distillation approach has many potential advantages for the commercial separation of ZrCl4 and HfCl4 compared to the conventional distillation because of its milder temperatures and pressure conditions, smaller number of required separation trays in the column, and lower energy requirement for separation, while still taking the advantage of environmentally benign feature by distillation. A heat-pump-assisted configuration was also explored to improve the energy efficiency of the extractive distillation process. The proposed enhanced configuration reduced the energy requirement drastically. Extractive distillation can be a promising option competing with the existing extraction-based separation process for zirconium purification for nuclear power reactor applications.

Highlights

  • Nuclear power has emerged as a reliable baseload source of electricity providing approximately13% of the world’s electrical power [1]

  • The optimal design of extractive distillation column and its enhanced configuration was studied with its main design condition using a rigorous commercial process simulator, Aspen HYSYS, and their performance was compared with conventional distillation

  • Based on the vapor-liquid equilibrium behavior of the ZrCl4 and HfCl4 mixture over the molten salts, as discussed in the previous section, a modified ANTOINE fluid package model [30] was selected from the Aspen HYSYS property library to simulate the vapor–liquid equilibrium and thermodynamic properties of the molten salt system

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Summary

Introduction

Nuclear power has emerged as a reliable baseload source of electricity providing approximately. Zirconium (Zr) alloy (or Zircaloy2) has many useful properties for applications in nuclear facilities, such as low absorption cross-section of thermal electrons, high ductility, good fabricability, hardness, and corrosion resistance [4,5]. These alloys are used widely as cladding and guide tubes in pressurized water-cooled reactors. A large portion of the entire processing facility for the production of Zr and Hf metals is dedicated to handling a multiple-step solvent extraction process in the presence of a solvent It generates a huge volume of liquid waste, which is difficult to dispose of due to stringent environmental protection laws [17,18,19,20]. The optimal design of extractive distillation column and its enhanced configuration was studied with its main design condition using a rigorous commercial process simulator, Aspen HYSYS, and their performance was compared with conventional distillation

Vapor–Liquid Equilibrium Model for ZrCl4 and HfCl4 Mixture over Molten Salts
Enhanced Configuration by Heat-Pump Assisted Self-Heat Integration Technique
Findings
Conclusions
Full Text
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