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A Report on the Interaction of the Nuclear and Power Plant Controls for the SRE Steam Electric Generating Station
Introduction: The purpose of this report is to describe in further detail the control systems that interconnect the SRE with the steam plant.
Date:
April 30, 1956
Creator:
unknown
System:
The UNT Digital Library
Quarterly report of the solution corrotion group for the period ending april 30, 1956
None
Date:
April 30, 1956
Creator:
Griess, J. C.; Savage, H. C.; English, J. L.; Greeley, R. S.; Buxton, S. R.; Warner, R. M. et al.
System:
The UNT Digital Library
Further Information on the Cake Formed During Slurry Test 200A-3
None
Date:
April 30, 1956
Creator:
Thomas, D. G.
System:
The UNT Digital Library
HRT COOLING WATER SYSTEM EVALUATION--RESULTS OF HRT ENGINEERING TESTS VI A- 2, 3, 4 5 B-1 a, b AND B-3
None
Date:
April 30, 1956
Creator:
Brooksbank, R.E.
System:
The UNT Digital Library
HRP DYNAMIC SLURRY CORROSION STUDIES: QUARTER ENDING APRIL 30, 1956
None
Date:
April 30, 1956
Creator:
Compere, E. L.; Savage, H. C.; Reed, S. A.; Moore, G. E.; Warner, R. M.; Pierce, R. M. et al.
System:
The UNT Digital Library
HRT Core and Blanket Vent Piping (Lines 127 and 227)
None
Date:
April 30, 1956
Creator:
McLain, H. A.
System:
The UNT Digital Library
ANCO Progress Report for Month of April 1956
This report talks about the ANCO Progress Report for month of April, 1956
Date:
April 30, 1956
Creator:
Drury, J. S.
System:
The UNT Digital Library
Chemical Development Status Report for Week Ending April 20, 1956
This is the Chemical Development Status Report for Week Ending April 20, 1956
Date:
April 30, 1956
Creator:
Blanco, R. E. & Ferguson, D. E.
System:
The UNT Digital Library
Quarterly Progress Report on Reactor Development 400 Program
Physics calculations have been made for various combinations of the four types of fuel assemblies to be used in the EBWR core. Two thicknesses of plates, 0.205 in. and 0.274 in., including the two 0.020-in. cladding layers, are to be made of both natural U and U containing 1.44% U235. A total of 148 assemblies, 74 natural and 74 enriched, are to be fabricated with six identical plates each. Various configurations of these fuel assemblies will be used to (1) change the critical size of the core, (2) change the power distribution in the core, and (3) change the amount of reactivity corresponding to a given stream volume in the core. The physics calculations show that uncertainties in critical mass are adequately covered by the number and variety of fuel assemblies and that the possible changes in core characteristics with the different fuel assemblies should provide valuable information about the factors affecting maximum power density and stability in a boiling water reactor.
Date:
April 30, 1956
Creator:
Stuart McLain & Members of the Laboratory Staff
System:
The UNT Digital Library