An optimization study for the reactor vessel auxiliary cooling system of a pool liquid-metal reactor

Journal Article · Mon Apr 01 00:00:00 EST 1991 · Nuclear Technology; (United States)

OSTI ID:5105972

Tzanos, C P; Tessier, H; Pedersen, D R ^[1]

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1. Argonne National Lab., Reactor Engineering Div., Argonne, IL (US)

This paper reports on the effects of design parameters on the performance of the reactor vessel auxiliary cooling system (RVACS) of a pool liquid-metal reactor (LMR). These parameters include stack height, size of the airflow gap, system pressure loss, fins on the guard vessel or the baffle wall, and repeated ribs on the airflow channel walls. As a measure of performance , the peak sodium pool temperature during transient following a reactor scram from full power was used. Horizontal ribs with a 0.003-m height and a 0.015-m pitch gave the best performance, i.e., the lowest peak sodium pool temperature during the scram transient. For a 3500-MW(thermal) LMR, they gave peak hot pool and peak cladding temperatures that were 52{degrees}C lower than those obtained with a reference RVACS having smooth airflow channel walls.

• OSTI ID: 5105972
• Journal Information: Nuclear Technology; (United States), Vol. 94:1; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
POOL TYPE REACTORS
REACTOR COOLING SYSTEMS
DESIGN
PERFORMANCE
CLADDING
OPTIMIZATION
PRESSURE DROP
REACTOR SAFETY
REACTOR VESSELS
TEMPERATURE MEASUREMENT
CONTAINERS
COOLING SYSTEMS
DEPOSITION
ENERGY SYSTEMS
REACTOR COMPONENTS
REACTORS
SAFETY
SURFACE COATING
WATER COOLED REACTORS
WATER MODERATED REACTORS
220200* - Nuclear Reactor Technology- Components & Accessories