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. / UOIT
| Identifer | oai:union.ndltd.org:LACETR/oai:collectionscanada.gc.ca:OOSHDU.10155/179 |
| Date | 01 July 2011 |
| Creators | Lukomski, Andrew John |
| Contributors | Gabriel, Kamiel, Pioro, Igor |
| Source Sets | Library and Archives Canada ETDs Repository / Centre d'archives des thèses électroniques de Bibliothèque et Archives Canada |
| Language | English |
| Detected Language | English |
| Type | Thesis |
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