Published 2011 | Version v1
Miscellaneous

Hydrogen production using process heat from an SCW NPP via a double-pipe heat exchanger

  • 1. Univ. of Ontario Inst. of Tech., Faculty of Energy Systems and Nuclear Science, Oshawa, ON (Canada)
  • 2. Univ. of Ontario Inst. of Tech., Faculty of Engineering and Applied Science, Oshawa, ON (Canada)

Description

The SuperCritical Water-cooled nuclear Reactor (SCWR) is one of six Generation-IV nuclear- reactor concepts currently under development worldwide. It is designed to operate at pressures of 25 MPa and temperatures up to 625oC. These operating conditions make an SCW Nuclear Power Plant (NPP) suitable to support thermochemical-based hydrogen co-generation. The Copper-Chlorine (Cu-Cl) cycle is a prospective thermochemical cycle with a maximum temperature requirement of ~530oC. Preliminary thermalhydraulic calculations are presented for a double-pipe counter-flow heat exchanger located downstream of an SCWR with no-steam- reheat cycle and with SCW coolant flowing through the inner pipe and steam flowing to the Cu-Cl cycle facility through the annulus. (author)

Part of:
ISSCWR-5. The 5th International Symposium on Supercritical-Water-Cooled Reactors

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-02-5
Imprint Title
ISSCWR-5. The 5th International Symposium on Supercritical-Water-Cooled Reactors
Imprint Pagination
90.1 Megabytes
Journal Page Range
[12 p.]

Conference

Title
5. International Symposium on Supercritical-Water-Cooled Reactors
Dates
13-16 Mar 2011
Place
Vancouver, BC (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
48068416
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
HEAT EXCHANGERS; HYDROGEN PRODUCTION; NUCLEAR POWER PLANTS; SUPERCRITICAL STATE; TURBULENT FLOW; WATER COOLED REACTORS
Descriptors DEC
FLUID FLOW; NUCLEAR FACILITIES; POWER PLANTS; REACTORS; THERMAL POWER PLANTS

Optional Information

Notes
24 refs., 3 tabs., 4 figs.