Study on linking a SuperCritical water-cooled nuclear reactor to a hydrogen production facility

The SuperCritical Water-cooled nuclear Reactor (SCWR) is one of six Generation-IV nuclear-reactor concepts currently being designed. It will operate at pressures of 25 MPa and temperatures up to 625°C. These operating conditions make a SuperCritical Water (SCW) Nuclear Power Plant (NPP) suitable to support thermochemical-based hydrogen production via co-generation. The Copper-Chlorine (Cu‒Cl) cycle is a prospective thermochemical cycle with a maximum temperature requirement of ~530°C and could be linked to an SCW NPP through a piping network. An intermediate Heat eXchanger (HX) is considered as a medium for heat transfer with operating fluids selected to be SCW and SuperHeated Steam (SHS). Thermalhydraulic calculations based on an iterative energy balance procedure are performed for counter-flow double-pipe design concept HXs integrated at several locations on an SCW NPP coolant loop. Using various test cases, design and operating parameters are recommended for detailed future research. In addition, predicted effects of heat transfer enhancement on HX parameters are evaluated considering theoretical improvements from helically-corrugated HX piping. The effects of operating fluid pressure drop are briefly discussed for applicability in future studies.

Name thesis:degree_name

Master of Applied Science (MASc)

Discipline thesis:degree_discipline

Nuclear Engineering

Grantor

University of Ontario Institute of Technology

Year dc:date.issued

2011

Author dc:creator

• Lukomski, Andrew John

Advisors dc:contributor.advisor

• Gabriel, Kamiel
• Pioro, Igor

• Hydrogen production
• Thermochemical cycles
• Copper-chlorine cycle
• Generation IV reactor
• SuperCritical water-cooled nuclear reactor
• Heat exchanger

Language dc:language.iso

en

Handle dc:identifier.uri

https://hdl.handle.net/10155/179

OAI identifier oai:identifier

oai:ontariotechu.scholaris.ca:10155/179