Port IV
Reactor Development
AIRCRAFT REACTORS @eaeee
Nuclear Propulsion for Manned Aircraft
Direct cycle approach. Work on the direct cycle approach was continued by the General
Electric Company under contracts with the AEC and the Air Force. The AEC {is supporting the
reactor portion of the effort and the Air Force is supporting the associated turbomachinery
work, The objective of the effort is to ground test by the fall of 1960 a nuclear propulsion system. The system, designated the XMA, consists of a preprototype reactor and associated X-211
turbomachinery.
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Preparations were being made for the operation during October of the Heat Transfer Reac~
tor Experiment No. 3 (HTRE-3) at the National Reactor Testing Station, This experiment is the
first of the HTRE series to have a horizontal configuration, a solid moderator, and a fifght-type
shield. The critical experiment for the HTRE-$ was completed and the fuel elements were |
modified for power operation. The dolly assembly, including engines and superstructure, was
completed except for fuel loading and final assembly.
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Modifications to the Initial Engine Test (IET) facility to accommodate the HTRE-3 were
completed. These modifications included instrumentation and supporting equipment and facilitiles such as 2 shielded approach roadway, for higher power operation. Construction work on
the Flight Erzine Test (FET) facility and the Shield Test Pool Facility (STPF) continued. The
purpose of the FET is to test full-scale, direct-cycle turbojet propulsion systems. The STPF
is a facility ccntaining a two-compartment pool for tests required in designing aircraft reactor
shielding.
Indirect cycle approach. Work continued on research and development applicable to a high
performance, indirect cycle aircraft reactor. Preliminary designs of two experimental reactors were being prepared as a further guide to the research effort on the Mthium-cooled, indirect-cycle system. Both designs called for reactors with a capacity of 10,000 thermal kilowatts and an 2bility to operate at temperatures between 1,800 and 2,000 degrees Fahrenheit.
One reactor Gesign was based on moderated neutrons at intermediate velocities while the
reactor of the other design was based on unmoderated neutrons at fast velocities. Preparations
were begun for the critical experiments to mockup the experimental reactor designs. In-pile
experiments were being conducted to verify the performance and integrity of the fuel elements
selected for the designs.
Continue2 testing verified previous results which indicated that an alloy of niobium and
zirconium is compatible with lithium at high temperatures. During operation of test loops the
alloy showed little or no effects from corrosion or mass transfer.
DOs ARCHIVES
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