Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

HELIUM AS A REACTOR COOLANT

Journal Article · · Progr. in Nuclear Energy, Ser. IV
OSTI ID:4800553

The combination of high thermal conductivity and specific heat coupled with chemical inertness gives helium unique advantages over any other gas as a reactor coolant. These advantages are particularly pronounced if the reactor is designed to operate at temperatures above 1000 deg F. Four major reactors are based on helium as the coolant, i.e., Dragon and Winfrith Heath, EGCR at Oak Ridge, HTGR near Philadelphia, and Turret at Los Alamos. In each instance helium was chosen in preference to carbon dioxide in an effort to avoid graphite-carbon dioxide reactions which lead to serious losses of graphite from the core and deposition of carbon in the steam generator or heat exchanger. (N.W.R.)

Research Organization:
Oak Ridge National Lab., Tenn.
NSA Number:
NSA-16-012832
OSTI ID:
4800553
Journal Information:
Progr. in Nuclear Energy, Ser. IV, Journal Name: Progr. in Nuclear Energy, Ser. IV Vol. Vol: 4
Country of Publication:
Country unknown/Code not available
Language:
English

Similar Records

DRAGON, DETAILS OF THE 10 MW HTGR
Journal Article · Tue Mar 31 23:00:00 EST 1959 · Nuclear Power · OSTI ID:4271065

FUEL UNLOADING MACHINE OF THE DRAGON REACTOR: AN INTERESTING SWISS ACHIEVEMENT IN THE NUCLEAR FIELD
Journal Article · Wed Apr 24 23:00:00 EST 1963 · Schweizerische Technische Zeitschrift (Switzerland) · OSTI ID:4164067

Technical Program Plan for INL Advanced Reactor Technologies Advanced Gas Reactor Fuel Development and Qualification Program
Program Document · Fri Jun 29 00:00:00 EDT 2018 · OSTI ID:1498779