DESIGN OF THE AMERICAN HIGH-TEMPERATURE REACTOR

Journal Article · Sun Jan 01 04:00:00 EST 1961 · Energia es Atomtech.

OSTI ID:4048861

Retvari, L

Although it represents only the prototyp stage, the HTGR has been designed for a relatively high heat-generating capacity with improved steam characteristics. It is hoped that a high burnout will be obtained from the sturdily constructed, reliable fuel elements, preserting a safe and efficient system. The maintenance problems are simplified by having only a low-level activity in the primary system. Comparing the operational parameters of the HTGR, the German BBC-Krupp and the British Dragon reactors, it is noted that all three of these high-temperature reactors use highly or completely enriched fuel, take advantage of the U-233 or the Th-232 formed, are designed for a high burnout, and have a fuel temperature higher than 1000 deg C resulting in a gas outlet temperature of about 800 deg C. In this latter respect they present a considerable improvement over the British gas-cooled reactors with gas outlet temperature of 400 deg C. The net yield of the HTGR will be about 35% which compares favorably with the 20 to 25% yield of the current British power reactors. The new high temperature reactor systems are of great interest to countries which recently bscanne interested in the utilization of nuclear energy. (TTT)

• Research Organization: Heat Planning Commission
• NSA Number: NSA-15-015298
• OSTI ID: 4048861
• Journal Information: Energia es Atomtech., Journal Name: Energia es Atomtech. Vol. Vol: 14
• Country of Publication: Country unknown/Code not available
• Language: Hungarian

Related Subjects

BURNUP
DRAGON
EFFICIENCY
ENRICHMENT
FUEL ELEMENTS
GAS COOLANT
HIGH TEMPERATURE
HTGR
MAINTENANCE
REACTOR TECHNOLOGY
REACTORS
THORIUM 232
URANIUM 233