An optimization study for the reactor vessel auxiliary cooling system of a pool liquid-metal reactor
Creators
- 1. Argonne National Lab., Reactor Engineering Div., Argonne, IL (United States)
Description
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
Additional details
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 94
- Journal Issue
- 1
- Series
- Nucl. Technol.
- Journal Page Range
- 68-79
- ISSN
- 0029-5450
- CODEN
- NUTYB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23022677
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CLADDING; DESIGN; OPTIMIZATION; PERFORMANCE; POOL TYPE REACTORS; PRESSURE DROP; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR VESSELS; TEMPERATURE MEASUREMENT
- Descriptors DEC
- CONTAINERS; COOLING SYSTEMS; DEPOSITION; REACTOR COMPONENTS; REACTORS; SAFETY; SURFACE COATING; WATER COOLED REACTORS; WATER MODERATED REACTORS