الفهرس 
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Abstract
The objective of this work is to develope a digital simulator a complete Pressurized Water Reactor Nucl~ar Power Plant (PWR¬P) capable of simulating accidents in which vapor may be genera¬in the reactor core and transported along the primary loop.
Extensive heat transfer correlations, two-phase friction mult¬; pIier, and thermodynamic properties covering a wide range of pre¬.sure and temperature are included.
Two models of the two-phase flow, one of which has been ads¬the other has been developed were implemented and respon¬,
compared. Although the void fraction, heat transfer coef¬ficients, and two-phase friction multiplier are defined differently two models, results obtained indicate negligible differen-
ces.
The Two-phase degraded electric torque of the reactor coolant pump motor, which is function of the cold leg temperature, is obta¬ined from empirical curves presented in post ’rhree Mile Island (TIfI) publications. Pump head is a function of pump speed and flow rate The hydrostatic head cal cula tions are valid not only in the subcoo¬led, but also in the two-phase regime.
The pressurizer is simulated as two-region double-ended conta¬iner with relief and safety valves at the top. Movable boundaries are utilized in modeling of the U-tube recirculation type stesm generator. Two-stage turbiae with interstage steam reheater, and a speed governer are included. Controllers for all plant components are incorporated.
In the reactor core,neutronic’s calculations, prompt Jump
(for P < 1$ ) / Nordheim - ruches (for P ~ 1 $) point and one-dimensional ( 1 n)time dependent two group .;.diffusion models are merged.
Besides operational transients, the code~~as been utilized simulating a 900 MW(e) PWRliPP response to: pressurizer relief valve opening, loss of electric power supply to the reac¬tor coolant pumps, and control rod ejection.