40-MW(E) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR POSTCONSTRUCTION RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Progress Report for the Period Ending April 30, 1970. [electronic resource]
Graphite/radiation Effects On Hydrogen Content Of, Neutron, (e); Steel/radiation Effects On Fracture Strength Of, Fast Neutron, (e); Neutrons, Fast/effects On Fracture Strength Of Pressure Vessel Steels, (e); Pressure Vessels/radiation Effects On Fracture Strength Of Peach Bottom, Fast Neutron, (e);...
Saved in:
| Online Access: |
Online Access |
|---|---|
| Corporate Author: | |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
San Diego, Calif. : Oak Ridge, Tenn. :
Gulf General Atomic Incorporated ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1970.
|
| Subjects: |
Control Elements
> Coolant Loops
> Distribution
> Failures
> Fast Neutrons
> Fission Products
> Fuel Cans
> Fuel Elements
> Graphite
> Impurities
> Inspection- - Particles
> Performance
> Pressure Vessels
> Radiation Effects
> Reflectors
> Remote Handling
> Shutdown
> Steels
> Tensile Properties
> Thermal Insulation.
|
Internet
Online AccessOnline
| Call Number: |
E 1.99:ga--10099
|
|---|---|
| E 1.99:ga--10099 | Available |