Explore Books on
gas cooled reactors
1-24 of 208 Books
Gas-cooled fast breeder reactor
Gas-cooled fast breeder reactor
By General Atomic Company.
HTGR process heat program
HTGR process heat program
By General Atomic Company.
Gas-cooled fast breeder reactor (GCFR) safety program plan (preliminary issue)
Gas-cooled fast breeder reactor (GCFR) safety program plan (preliminary issue)
By General Atomic Company. GCFR Staff
HTGR generic technology program
HTGR generic technology program
By General Atomic Company.
Non-proliferaton cycles, Core design plans
Non-proliferaton cycles, Core design plans
By A. M. Baxter
ORCULT-I, a loop dynamics simulator program for the core flow test loop
ORCULT-I, a loop dynamics simulator program for the core flow test loop
By S. J Ball
ORCULT-I, a loop dynamics simulator program for the core flow test loop
ORCULT-I, a loop dynamics simulator program for the core flow test loop
By S. J. Ball
Physics of high-temperature reactors
By Luigi Massimo
Gas-cooled reactors with emphasis on advanced systems
By Symposium on Gas-Cooled Reactors with Emphasis on Advanced Systems Jülich 1975.
0.20-m (8-in.) primary burner development report
0.20-m (8-in.) primary burner development report
By R. T Stula
Materials behavior in HTGR environments
Materials behavior in HTGR environments
By K. Natesan
Evaluation of MHTGR fuel reliability
Evaluation of MHTGR fuel reliability
By R. P. Wichner
High-temperature gas-cooled reactor base-technology program
High-temperature gas-cooled reactor base-technology program
By F. J Homan
High-temperature gas-cooled reactor fuel recycle development
High-temperature gas-cooled reactor fuel recycle development
By A. L Lotts
The irradiated-microsphere gamma analyzer (IMGA)
The irradiated-microsphere gamma analyzer (IMGA)
By M. J Kania
Effect of particle blending on HTGR fuel rod temperature profiles
Effect of particle blending on HTGR fuel rod temperature profiles
By P. Angelini
High-temperature gas-cooled reactor base-technology program
High-temperature gas-cooled reactor base-technology program
By F. J. Homan
Three-dimensional thermoelastic analysis of a Fort S. Vrain core support block
Three-dimensional thermoelastic analysis of a Fort S. Vrain core support block
By Thomas A Butler
Assessment of grade H-451 graphite for replaceable fuel and reflector elements in HTGR
Assessment of grade H-451 graphite for replaceable fuel and reflector elements in HTGR
By G. B. Engle
In-line tritium monitoring in the GCFR vented irradition capsule GB-10
In-line tritium monitoring in the GCFR vented irradition capsule GB-10
By M. E Pruitt
Medium-enriched uranium/thorium fuel cycle parametric studies for the HTGR
Medium-enriched uranium/thorium fuel cycle parametric studies for the HTGR
By M. H. Merrill
Flow-induced vibrations in the 300-MW(e) gas-cooled fast breeder reactor demonstration plant
Flow-induced vibrations in the 300-MW(e) gas-cooled fast breeder reactor demonstration plant
By L. J. Halvers
In-line tritium monitoring in the GCFR vented irradition capsule GB-10
In-line tritium monitoring in the GCFR vented irradition capsule GB-10
By M. E. Pruitt