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1
Problems in the manufacture of steam surface condensers for nuclear power stations
Material Type:
Report
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Problems in the manufacture of steam surface condensers for nuclear power stations

Nagi, S.K.

India 1973

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2
Economics of the use of surface condensers with dry-type cooling systems for fossil-fueled and nuclear generating plants
Material Type:
Report
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Economics of the use of surface condensers with dry-type cooling systems for fossil-fueled and nuclear generating plants

Rossie, J.P. ; Mitchell, R.D. ; Young, R.O.

United States 1973

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3
Report of current standards for condensers and condensing system pumps for air-cooled steam power plants
Material Type:
Report
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Report of current standards for condensers and condensing system pumps for air-cooled steam power plants

Beck (R.W.) and Associates, Denver, Colo. (USA)

United States 1973

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4
Use a Vent Condenser to Recover Flash Steam Energy - Steam Tip Sheet #13
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Report
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Use a Vent Condenser to Recover Flash Steam Energy - Steam Tip Sheet #13

EERE Publication and Product Library, Washington, D.C. (United States)

United States 2012

Sem texto completo

5
Cooling of nuclear power stations
Material Type:
Report
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Cooling of nuclear power stations

Sasek, J. Page

Serbia and Montenegro 1973

Sem texto completo

6
Restoration of the USS Monitor
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Report
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Restoration of the USS Monitor

Krop, David

United States 2010

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7
Treatment of Cooling Waters with Chlorine
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Report
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Treatment of Cooling Waters with Chlorine

Draley, J. E

Argonne National Laboratory 1972

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8
TREATMENT OF COOLING WATERS WITH CHLORINE
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Report
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TREATMENT OF COOLING WATERS WITH CHLORINE

Draley, J.E.

United States 1972

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9
Computational fluid dynamics modeling of two-phase flow in a BWR fuel assembly. Final CRADA Report
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Report
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Computational fluid dynamics modeling of two-phase flow in a BWR fuel assembly. Final CRADA Report

Tentner, A ; Argonne National Laboratory. Nuclear Engineering Division

Argonne National Laboratory 2009

Sem texto completo

10
Computational fluid dynamics modeling of two-phase flow in a BWR fuel assembly. Final CRADA Report
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Report
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Computational fluid dynamics modeling of two-phase flow in a BWR fuel assembly. Final CRADA Report

Tentner, A ; Nuclear Engineering Division

United States 2009

Sem texto completo

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