Computer Programs

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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To submit a request, click below on the link of the version you wish to order. Rules for end-users are
available here.

Program name | Package id | Status | Status date |
---|---|---|---|

SURGTANK | NESC0853/01 | Arrived | 16-MAY-2001 |

Machines used:

Package ID | Orig. computer | Test computer |
---|---|---|

NESC0853/01 | IBM 360 series |

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3. DESCRIPTION OF PROBLEM OR FUNCTION

SURGTANK generates the steam pressure, saturation temperature, and ambient temperature history for a nuclear reactor steam surge tank (pressurizer) in a state of thermodynamic equilibrium subjected to a liquid insurge described by a specified time history of liquid levels. It is capable also of providing the pressure and saturation temperature history, starting from thermodynamic equilibrium conditions, for the same tank sub- jected to an outsurge described by a time history of liquid levels.

Both operations are available for light- or heavy- water nuclear reactor systems. The tank is assumed to have perfect thermal insu- lation on its outer wall surfaces.

SURGTANK generates the steam pressure, saturation temperature, and ambient temperature history for a nuclear reactor steam surge tank (pressurizer) in a state of thermodynamic equilibrium subjected to a liquid insurge described by a specified time history of liquid levels. It is capable also of providing the pressure and saturation temperature history, starting from thermodynamic equilibrium conditions, for the same tank sub- jected to an outsurge described by a time history of liquid levels.

Both operations are available for light- or heavy- water nuclear reactor systems. The tank is assumed to have perfect thermal insu- lation on its outer wall surfaces.

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4. METHOD OF SOLUTION

Surge tank geometry and initial liquid level and saturation pressure are provided as input for the outsurge pro- blem, along with the prescribed time-sequence level history.

SURGTANK assumes a reduced pressure for the end of the first change in liquid level and determines the associated change of entropy for the closed system. The assumed pressure is adjusted and the associa- ted change in entropy recalculated until a pressure is attained for which no change occurs. This pressure is recorded and used as the beginning pressure for the next level increment. The system is then re-defined to exclude the small amount of liquid which has left the tank, and a solution for the pressure at the end of the second level increment is obtained. The procedure is terminated when the pressure at the end of the final increment has been determined.

Surge tank geometry, thermal conductivity, specific heat, and density of tank walls, initial liquid level, and saturation pressure are provided as input for the insurge problem, along with the pres- cribed time-sequence level history. SURGTANK assumes a slightly in- creased pressure for the end of the first level, the inner tank sur- face is assumed to follow saturation temperature, linearly with time, throughout the interval, and the heat transferred to the walls and down into the liquid content of the tank is computed. The equa- tion of state is utilized to obtain ambient temperature at the end of the interval. Deviations of the steam from perfect gas theory are taken into account. An energy balance is determined for the end of interval in keeping with the first law of thermodynamics. Any im- balance is designed as error, stored, and the procedure is repeated with a slightly higher assumed pressure. These calculations are re- peated until a change in sign of the error is noted, and the exact pressure can be determined. The properties calculated for the end of the first level and time increment are used as the starting proper- ties of the second increment, etc. Calculations are terminated when the final level is reached.

Surge tank geometry and initial liquid level and saturation pressure are provided as input for the outsurge pro- blem, along with the prescribed time-sequence level history.

SURGTANK assumes a reduced pressure for the end of the first change in liquid level and determines the associated change of entropy for the closed system. The assumed pressure is adjusted and the associa- ted change in entropy recalculated until a pressure is attained for which no change occurs. This pressure is recorded and used as the beginning pressure for the next level increment. The system is then re-defined to exclude the small amount of liquid which has left the tank, and a solution for the pressure at the end of the second level increment is obtained. The procedure is terminated when the pressure at the end of the final increment has been determined.

Surge tank geometry, thermal conductivity, specific heat, and density of tank walls, initial liquid level, and saturation pressure are provided as input for the insurge problem, along with the pres- cribed time-sequence level history. SURGTANK assumes a slightly in- creased pressure for the end of the first level, the inner tank sur- face is assumed to follow saturation temperature, linearly with time, throughout the interval, and the heat transferred to the walls and down into the liquid content of the tank is computed. The equa- tion of state is utilized to obtain ambient temperature at the end of the interval. Deviations of the steam from perfect gas theory are taken into account. An energy balance is determined for the end of interval in keeping with the first law of thermodynamics. Any im- balance is designed as error, stored, and the procedure is repeated with a slightly higher assumed pressure. These calculations are re- peated until a change in sign of the error is noted, and the exact pressure can be determined. The properties calculated for the end of the first level and time increment are used as the starting proper- ties of the second increment, etc. Calculations are terminated when the final level is reached.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The program was de- veloped for predicting pressure behavior in vertical axis cylind- drical tanks with spherical dome caps. It could be readily adapted to other geometries, such as spherical tanks (reference 2). Back-to- back insurges and outsurges cannot be treated since each must start from equilibrium conditions. The analysis does not include the effects of heaters, sprays, and safety valves. Possible modifica- tions to include effects of sprays are discussed in reference 5.

The program was de- veloped for predicting pressure behavior in vertical axis cylind- drical tanks with spherical dome caps. It could be readily adapted to other geometries, such as spherical tanks (reference 2). Back-to- back insurges and outsurges cannot be treated since each must start from equilibrium conditions. The analysis does not include the effects of heaters, sprays, and safety valves. Possible modifica- tions to include effects of sprays are discussed in reference 5.

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6. TYPICAL RUNNING TIME

The average running time to obtain a pressure -time history for a prototype steam surge tank is about 14 minutes for insurge problems and about 4 minutes for outsurge problems on an IBM360/65. Time for the actual insurge and outsurge processes is about 2 minutes. NESC executed the sample insurge problem in 172 CPU seconds and the outsurge problem in 260 CPU seconds on the IBM3033.

The average running time to obtain a pressure -time history for a prototype steam surge tank is about 14 minutes for insurge problems and about 4 minutes for outsurge problems on an IBM360/65. Time for the actual insurge and outsurge processes is about 2 minutes. NESC executed the sample insurge problem in 172 CPU seconds and the outsurge problem in 260 CPU seconds on the IBM3033.

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10. REFERENCES

- E.E. Drucker and D.J. Gorman,

A Method of Predicting Steam Surge Tank Transients Based on one

Dimensional Heat Sinks,

Nuclear Science and Engineering, Vol. 21, pp. 473-480, 1965.

- D.J. Gorman,

Steam Surge Tank Transients During Outsurge,

American Society of Mechanical Engineers Paper 69-WA/NE14, ASME

Winter Annual Meeting, Los Angeles, California, November 16-20,

1969.

- D.J. Gorman,

Pressure Behavior in Pressurized Steam Surge Tanks, Appendices B

and C, M.S. Thesis,

Department of Mechanical and Aerospace Engineering, Syracuse Uni-

versity, Syracuse, New York, 1962.

- E.E. Drucker and D.J. Gorman,

A Method of Predicting Steam Surge Tank Transients Based on one

Dimensional Heat Sinks,

Nuclear Science and Engineering, Vol. 21, pp. 473-480, 1965.

- D.J. Gorman,

Steam Surge Tank Transients During Outsurge,

American Society of Mechanical Engineers Paper 69-WA/NE14, ASME

Winter Annual Meeting, Los Angeles, California, November 16-20,

1969.

- D.J. Gorman,

Pressure Behavior in Pressurized Steam Surge Tanks, Appendices B

and C, M.S. Thesis,

Department of Mechanical and Aerospace Engineering, Syracuse Uni-

versity, Syracuse, New York, 1962.

NESC0853/01, included references:

- R.K. Gupta:The Analysis and Computation of Steam Surge Tank Dynamics for

Light and Heavy Water Systems

M. S. thesis, Department of Mechanical Engineering, University of

Ottawa, Ottawa, Canada, (August 1972).

- D.J. Gorman and R.K. Gupta:

SURGTANK, Listing of Computer Input Symbols

University of Ottawa Note, (July 5, 1977).

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NESC0853/01

source program mag tapeINSURGE Source Program SRCTPsource program mag tapeOUTSURGE Source Program SRCTP

test-case data mag tapeINSURGE Sample Problem Input DATTP

test-case data mag tapeOUTSURGE Sample Problem Input DATTP

test-case output listing Sample Problem Output OUTLS

report M.S. Thesis U. Ottawa (August 1972) REPPT

user's guide List. of Computer Input Symb. (07-05-1977) WRKPT

Keywords: LWR reactors, heavy water cooled reactors, pressure, pressure vessels, pressurizers, reactor cooling systems, steam, temperature, thermodynamics, transients, water cooled reactors.