Published April 2017 | Version v1
Miscellaneous Metadata-only

System level thermal-hydraulic assessment of a natural circulating LFR

Creators

  • 1. Massachusetts Institute of Technology, Cambridge, MA (United States)
  • 2. Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)
  • 3. Seoul National University, Seoul (Korea, Republic of)

Description

Light Water Reactor Small Modular Reactors (LWR SMRs) have struggled to penetrate the US and international electricity markets while solar and wind energy have experienced tremendous success. Lead Fast Reactor (LFR) technology has great potential as an alternative to LWR SMRs to be able to complement solar and wind energy to produce baseload carbon free electricity. The inherent properties of lead coolant results in high degree of safety, plant simplification and design compactness. This study focuses on thermal-hydraulic performance of a natural circulating Lead-Bismuth Eutectic (LBE) cooled reactor with passive air cooling safety system. Specifically, the LFR design's response during steady state and ultimate loss of heat sink accident to thermal hydraulic model perturbations is shown to be insensitive. (author)

Part of:
Proceedings of 2017 international congress on advances in nuclear power plants (ICAPP2017)

Additional details

Publishing Information

Imprint Title
Proceedings of 2017 international congress on advances in nuclear power plants (ICAPP2017)
Imprint Pagination
2573 p.
Journal Page Range
7 p.

Conference

Title
2017 international congress on advances in nuclear power plants
Acronym
ICAPP2017
Dates
24-25 Apr 2017; 26-28 Apr 2017
Place
Fukui (Japan); Kyoto (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
49033582
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CORRELATIONS; FAST REACTORS; FUEL PINS; HEAT SINKS; LIQUID METAL COOLED REACTORS; M CODES; NATURAL CONVECTION; NUSSELT NUMBER; R CODES; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR SAFETY; REACTOR VESSELS; STEAM GENERATORS; THERMAL HYDRAULICS
Descriptors DEC
ACCIDENTS; BOILERS; COMPUTER CODES; CONTAINERS; CONVECTION; COOLING SYSTEMS; DIMENSIONLESS NUMBERS; ENERGY SYSTEMS; ENERGY TRANSFER; EPITHERMAL REACTORS; FLUID MECHANICS; FUEL ELEMENTS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MECHANICS; REACTOR COMPONENTS; REACTORS; SAFETY; SINKS; VAPOR GENERATORS

Optional Information

Notes
Available as CD-ROM Data in PDF format. Folder Name: pdf; Paper ID: 17641.pdf; 12 refs., 10 figs., 2 tabs.