ML19260C567

Forwards Progress Rept Summarizing Lumped Parameter Conservation Equations for Fixed Control Vol Consisting of Three Regions Divided by Two Moving Boundaries

ML19260C567
Person / Time
Issue date:	12/08/1979
From:	Zuber N NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:	Tong L NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
References
791228, NUDOCS 8001080006
Download: ML19260C567 (30)

Text

/D DW o

UNITED STATES 8

NUCLEAR REGULATORY COMMISSION g

j WASHINGTON, D, C. 20555

..... e/

DEC2 81979 s

MEMORANDUM FOR:,L. S. Tong, Assistant Director for Water Reactor Safety Research, RSR THRU:

S. Fabic, Chief Analysis Development Branch, RSR FROM:

N. Zuber Analysis Development Branch, RSR

SUBJECT:

TRANSMITTAL OF PROGRESS REPORT ENTITLED:

" LUMPED PARAMETER MOVING B0UNDARY MODEL" I am enclosing the above mentioned progress report which summarizes lumped-parameter conservation equations for a fixed control volume consisting of three regions divided by two moving boundaries.

Two of these regions are single phase, whereas the middle one contains a two-phase mixture.

For the latter, the conservation equa'tions are based on the drift-flux model. The purpose for deriving these equations is as follows:

In July 1979, EAI submitted an unsolicited proposal to the NRC to investigate the feasibility of using a hybrid (analog / digital) methodology in advanced (engineering) simulator. Their proposal stipulated a 3 month project during which the necessary thermo-hydraulic equations for a PWR pressurizer would be solved via hybrid method in order to help the NRC make a judgment concerning advantages of a hybrid vs pure digital approach.

We found the EAI proposal of sufficiend interest to merit a careful consideration. However, upon reviewing the proposal we concluded that the proposed thennohydraulic equations were inadequate, so that a correct assessment of hybrid vs pure digital approach could not have been achieved by solving them.

In view of NRC's interest to use advanced simulators for small break LOCA calculations, S. Fabic asked me to fonnulate the simplest model which could be used to assess the merits of a hybrid vs digital solution method.

It was stipulated that the model should have the capability to track interfaces (thermal and/or hydraulic such as froth level) and account for the effects of phase separation and thennal nonequilibrium. One solution which would meet these requirements is a formulation based on a lumped-parameter, moving boundary, drift flux model.

The 1701 115 8001080

• 006

r L. S. Tong advantage of a moving boundary model when compared to a fixed mesh t-formulation, is that it offers a way to track accurately interfaces as well as to reduce the number of control volumes.

The latter is

1. ~-

desirable to assure fast running calculations.

I formulated therefore such a model and applied it to a control volume consisting of three regions divided by two moving boundaries.

Although simple, these regions are representative of those that will have to be modeled during a small break LOCA, for example those in a pressurizer.

Consequently, the conservation equations shown in the enclosure, and in particular the equations 3-11, 5-1, 5-2, 5-3, 6-1, 6-2, 6-3 and 7-4, can be used to assess the merit of hybrid vs digital solution method.

I should stress in closing, that this is a progress report which presents only a summary of the lumped-parameter, moving boundary conservation equations.

It does not discuss in detail all the assumptions, it does not list the nomenclature and appropriate bibliography. Neither does it contain the appropriate constitutive equations and correlations which are needed for closure. All these will be presented in a forthcoming report.

I should note also, that this set of equations is still too complex to assure fast running calculations.

Consequently, further simplifications based on engineering judgment, are needed to meet this objective.

As part of this ongoing work I introduced some simplifications, valid for small break LOCA's, whereby some of the equations can be pre-solved. Thus, the number of differential equations which need to be solved via a computer can be reduced by almost a half. These simplifications, together with the solution method will be pre-sented in the'above mentioned report.

W N. Zuber Analysis Development Branch Division of Reactor Safety Research

Enclosure:

as stated cc w/ enc 1:

T. E. Murley, RSR R. Fraley, ACRS R. Scroggins, ARCS H. Sullivan, RSR R. Di Salvo, PAS L. Beltracchi, DSS PDR(2) 1701 116

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