Digital computer program for nuclear reactor design water properties (LWBR Development Program)

Technical Report · Sat Jul 01 04:00:00 EDT 1967

OSTI ID:7011658

Lynn, L L

An edit program MO899 for the tabulation of thermodynamic and transport properties of liquid and vapor water, frequently used in design calculations for pressurized water nuclear reactors, is described. The data tabulated are obtained from a FORTRAN IV subroutine named HOH. Values of enthalpy, specific volume, viscosity, and thermal conductivity are given for the following ranges: pressure from one bar (14.5 psia) to 175 bars (2538 psia) and temperature from as much as 320 deg C (608 deg F) below saturation up to 500 deg C (932 deg F) above saturation. (NSA 21: 38472)

• Research Organization: Bettis Atomic Power Lab., Pittsburgh, PA (USA)
• DOE Contract Number: AT(11-1)-GEN-14
• OSTI ID: 7011658
• Report Number(s): WAPD-TM-680
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BREEDER REACTORS
COMPUTER CODES
COOLANTS
COOLING SYSTEMS
FLUID MECHANICS
FORTRAN
HYDRAULICS
HYDROGEN COMPOUNDS
LWBR TYPE REACTORS
M CODES
MECHANICS
OXYGEN COMPOUNDS
PHYSICAL PROPERTIES
PROGRAMMING LANGUAGES
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
STEAM
THERMAL REACTORS
THERMODYNAMIC PROPERTIES
THERMODYNAMICS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS