Published March 2015 | Version v1
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Technology Demonstration for Gen IV SFR

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Description

Construction of Sodium Thermal-hydraulic Test Facility and Integral Effect Test - Performance Test using STELLA-1 facility - Basic Design of a Large-scale Sodium Integral Effect Test Facility, STELLA-2. Demonstration of SFR Main Component Design - Performance tests for control rod drive mechanism and control rod free drop - Dynamic characteristic tests for upper internal structure - Development of ISI application technologies for reactor internal structure and demonstration tests - Performance test of SG tube inspection system - Performance test of reactor vessel inspection system - Performance test of high performance under-sodium viewing sensor. Thermal-Hydraulic Validation Tests of Sodium-cooled Fast Reactor Computer Codes - Validation test on flow characteristics of reactor core sub-channel - Heat transfer and flow characteristic tests on FHX - IHX flow characteristic tests. Study on the New Concept for Safety Enhancement of an SFR - Na-CO2 Interaction Tests - CO2 Leak Detection Tests - Removal of Reaction Products of Na-CO2.

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Additional details

Publishing Information

Imprint Pagination
367 p.
Report number
KAERI/RR--3856/2014

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
49108162
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
CONTROL ELEMENTS; DESIGN; HEAT TRANSFER; LEAKS; PERFORMANCE TESTING; SAFETY; SENSORS; SODIUM COOLED REACTORS; TEST FACILITIES; THERMAL HYDRAULICS; USES; VALIDATION
Descriptors DEC
ENERGY TRANSFER; FLUID MECHANICS; HYDRAULICS; LIQUID METAL COOLED REACTORS; MECHANICS; REACTOR COMPONENTS; REACTORS; TESTING

Optional Information

Notes
146 refs, 225 figs, 91 tabs