ORTURB: A Digital Computer Code to Determine the Dynamic Response of the Fort St. Vrain Reactor Steam Turbines
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
ORTURB is a computer code written specifically to calculate the dynamic behavior of the Fort St. Vrain (FSV) High-Temperature Gas-Cooled Reactor (HTGR) steam turbines. The ORTURB program can be independently exercised but is intended to be used in the overall FSV plant simulator code ORTAP currently under development at Oak Ridge National Laboratory. ORTURB uses a relationship derived for ideal gas flow in an iterative fashion that minimizes computational time to determine the pressure and flow in the FSV steam turbines as a function of plant transient operating conditions. An important computer modeling characteristic, unique to FSV, is that the high-pressure turbine exhaust steam is used to drive the reactor core coolant circulators prior to entering the reheater. A feedwater heater dynamic simulation model utilizing seven state variables for each of the five heaters completes the ORTURB computer simulation of the regenerative Rankine cycle steam turbines.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE; USNRC
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5053021
- Report Number(s):
- NUREG/CR--1789; ORNL/NUREG/TM--399; ON: TI86002670
- Country of Publication:
- United States
- Language:
- English
Similar Records
Dynamic computer simulation of the Fort St. Vrain steam turbines
High-Temperature Gas-Cooled Reactor Safety Studies for the Division of Reactor Safety Research Quarterly Progress Report, July 1-September 30, 1979
Developmental assessment of the Fort St. Vrain version of the Composite HTGR Analysis Program (CHAP-2)
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:6347919
High-Temperature Gas-Cooled Reactor Safety Studies for the Division of Reactor Safety Research Quarterly Progress Report, July 1-September 30, 1979
Technical Report
·
Mon Dec 31 19:00:00 EST 1979
·
OSTI ID:5713491
Developmental assessment of the Fort St. Vrain version of the Composite HTGR Analysis Program (CHAP-2)
Conference
·
Mon Dec 31 23:00:00 EST 1979
·
OSTI ID:5206500
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
97 MATHEMATICS AND COMPUTING
COMPUTER CALCULATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
DYNAMIC FUNCTION STUDIES
ENRICHED URANIUM REACTORS
FEEDWATER HEATERS
FLOW RATE
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEATERS
HELIUM COOLED REACTORS
HIGH PRESSURE
HTGR TYPE REACTORS
MACHINERY
O CODES
POWER REACTORS
RANKINE CYCLE
REACTORS
SIMULATION
STEAM TURBINES
THERMODYNAMIC CYCLES
TURBINES
TURBOMACHINERY
VRAIN REACTOR
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
97 MATHEMATICS AND COMPUTING
COMPUTER CALCULATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
DYNAMIC FUNCTION STUDIES
ENRICHED URANIUM REACTORS
FEEDWATER HEATERS
FLOW RATE
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEATERS
HELIUM COOLED REACTORS
HIGH PRESSURE
HTGR TYPE REACTORS
MACHINERY
O CODES
POWER REACTORS
RANKINE CYCLE
REACTORS
SIMULATION
STEAM TURBINES
THERMODYNAMIC CYCLES
TURBINES
TURBOMACHINERY
VRAIN REACTOR