-
1
Design study : sodium modular reactor
[Place of publication not identified] : Washington, D.C. : General Electric ; Available from the Office of Technical Services, U.S. Dept. of Commerce, 1960Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
2
Sodium Reactor Experiment (SRE) shielding evaluation for thermal neutron streaming at reactor vessel coolant pipe penetrations
Canoga Park, California : Atomics International, 1959Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
3
Corrosion and activity transfer in the SRE primary sodium system
Canoga Park, Calif. : Atomics International, A Division of North American Aviation, Inc., 1961Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
4
Power and flow ramp stability tests on the SRE
Canoga Park, California : Atomics International, 1962Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
5
Two-group calculation of the critical core size of the SRE reactor
Canoga Park, California : Atomics International, 1956Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
6
Study of SCTI control system
Canoga Park, Calif. : Atomics International, 1964Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
7
Reflected reactor kinetics
Canoga Park, California : Atomics International, 1963Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
8
Design and development of the safety-rod drop-time test system
Canoga Park, California : Atomics International, 1963Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
9
Analysis of power ramps with an analog computer
Canoga Park, California : Atomics International, 1964Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
10
Development of a process for sodium bonding of EBR-II fuel and blanket elements
Argonne, Ill. : Argonne National Laboratory, Reactor Engineering Division, 1961Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
11
Carburization of austenitic stainless steel in liquid sodium
Canoga Park, California : Atomics International, a division of North American Aviation, Inc., 1960Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
12
Sodium flow distribution in test fuel assembly P-23B
Richland, Wash. : [Springfield, Va.] : Dept. of Energy, Hanford Engineering Development Laboratory ; [for sale by the National Technical Information Service], 1978Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
13
Feasibility study of a 1000-Mwe sodium-cooled fast reactor.
[Oak Ridge, Tennessee] : Springfield, Va. : Division of Technical Information, U.S. Atomic Energy Commission ; Available from the Clearinghouse for Federal Scientific and Technical Information, 1966Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
14
Preapplication safety evaluation report for the power reactor innovative small module (PRISM) liquid-metal reactor : final report.
Washington, DC : Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1994Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
15
Simplified formulas and curves for bellows analysis
Washington, D.C. : Office of Technical Services, 1964Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
16
The non-linear behavior of large permanent-magnet flowmeters
Canoga Park, California : Washington, D.C. : Atomics International, A Division of North American Aviation, Inc. ; Available from the Office of Technical Services, 1960Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
17
10 MWe sodium deuterium reactor design report
Oak Ridge, Tenn. : Technical Information Service, 1959Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
18
The experimental development of a fuel handling system for the Sodium Reactor Experiment
Canoga Park, California : Atomics International, 1958Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
19
An evaluation of reactor concepts for use as separate steam superheaters
Argonne, Ill. : Argonne National Laboratory, Reactor Engineering Division, 1961Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?> -
20
Preliminary test of natural-circulation double-tube steam generator
Canoga Park, Calif. : Atomics International, 1959Format: Government Document Book
//IF NOT LOGGED IN - FORCE LOGIN ?>
//ELSE THEY ARE LOGGED IN PROCEED WITH THE OPEN URL CODE:?>