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NEA-0779 THYDE-P2, THYDE-W

THYDE-P, PWR LOCA Thermohydraulic Transient Analysis

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1. NAME OR DESIGNATION OF PROGRAM:  THYDE-P, THYDE-P2, THYDE-W.
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2. COMPUTERS
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Program name Package id Status Status date
THYDE-P2 NEA-0779/02 Tested 27-FEB-1989
THYDE-W NEA-0779/03 Arrived 16-MAY-2001

Machines used:

Package ID Orig. computer Test computer
NEA-0779/02 FACOM VP-100 IBM 3090
NEA-0779/03 FACOM M-780
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3. DESCRIPTION OF PROBLEM OR FUNCTION

THYDE-P1 analyzes the behaviour of LWR plants in response to various disturbances, including the thermal hydraulic transient following a break of the primary coolant pipe system, generally referred to as a loss-of-coolant-accident (LOCA). LOCA can be considered as the most critical condition for testing the methods and models for plant dynamics, since thermal hydraulic conditions in the system change drastically during the transient. THYDE-P is capable of a complete LOCA calculation from start to complete reflooding of the core by subcooled water. The program performs steady-state adjustment, which is complete in the sense that the steady state obtained is a set of exact solutions of  all the transient equations without time derivatives, not only for plant hydraulics but also for all the other phenomena in the simula- tion of a PWR plant.



THYDE-P2 contains among others the following improvements over THYDE-P1: (1) not only the mass and momentum equations but also the  energy equation are included in the non-linear implicit scheme; (2) the valve model is implemented; (3) the relaxation equation for  void fraction is theoretically derived; (4) vectorized programming is implemented; (5) both EM (evaluation mode) and BE (best estimate) calculations are possible.



THYDE-W is an improved version of THYDE-P2 and contains the following additional features: (a) analysis of multiple number of disjoint loops is possible; (b) a control system simulation model is included; (c) the trip model has been improved; (d) heavy water is allowed as coolant; (e) the effect of drift flux is accounted for in the steady state calculation; (f) boron transport is included; (g) to obtain steady state loop heat balance, the option of adjusting the enthalpy distribution is prepared included in addition to that of adjusting heat exchanger areas; (h) to obtain steady state pressure distribution, three other options are prepared in addition to the original ones. - The most important feature of THYDE-W is the conservation of mass, momentum and energy.
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4. METHOD OF SOLUTION

In THYDE-P, a PWR plant is regarded as a net- work of various coolant components which may be classified into nodes and junctions. The one-dimensional mass, momentum and energy equations are suitably integrated in each node and junction. In integrating the resulting equations with respect to time, a non- linear implicit method is used on the basis of the Newton method.
The Jacobian matrix of the basic equations can be reduced to a simple form by the network theory, which is one of the characteri- stics of THYDE-P. To solve the basic equations by the non-linear implicit method, various smoothing functions with respect to time are introduced for mode changes such as phase change and flow re- versal.

New models for a steam generator and a pressurizer are imple- mented.

A THYDE-P calculation is started by a steady-state adjustment, where the basic equations are exactly solved without time deriva- tives. THYDE-P is able to calculate through both blowdown and re- fill-reflood phases without any change of models and physical con- ditions of the coolant. A model which takes non-equilibrium effects  into account is newly implemented.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

It is required that  the network has at least one mixing junction except for the core heatup calculation mode and that a normal node without heat source (or sink) must be placed at both the top and bottom ends of the core. After so reticulating the plant, we have a number of nodes and junctions separately, strictly in numeric order in accordance with the following rules:

(a) Normal nodes (except linkage nodes) should be numbered in numer- ical order chain-wise from one mixing junction to another according  to the direction of the steady state chain flow.

(b) Then linkage nodes should be numbered in numeric order chain- wise from the corresponding mixing junction.

(c) Special nodes should be numbered after all the normal and linkage nodes.

(d) Among junctions, normal and guillotine break junctions should be numbered first. Then the mixing junctions should be numbered according to the direction of the steady-state flow. After these, the injection junctions and finally the dead-end junctions should be numbered.

(e) In the present version of THYDE-P, it is required that either of the hot leg nodes adjacent to the upper plenum mixing junction must be numbered as one and that the upper plenum should be numbered first among the mixing junctions.
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6. TYPICAL RUNNING TIME

THYDE-P: The sample problem with 101 time steps required 76 seconds of CPU time on the IBM 3081.
THYDE-W: The calculation of a 130 seconds cold leg large break LOCA  of a 4-loop PWR required 31 minutes 40 seconds (on a FACOM-VP-2600).
NEA-0779/02
NEA-DB ran the test case on an IBM 3090 computer for a
prefixed time of 4 minutes and 19 seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM

One of the characteristics of THYDE-P is its time step control. At each time step, the norm of the state vector of the primary loop network will be calculated. Let the ratio of the norm of the increment of the state vector in delta-t be REL. If REL is greater than EPS (an input value), the time step will be reduced by half, and the calculation is to be done over again. If REL is less than EPS/10, then the calculation proceeds to the next time step which has twice as large a width as the last. If REL is in between EPS and EPS/10, then the next time step calculation is to be done with the same time step width as the last.
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8. RELATED AND AUXILIARY PROGRAMS

The THYDE-P plotting system dis- plays results on a cathode-ray tube or film, coupling data sets generated in a series of THYDE-P runs. The data for the plotting system are stored in a data set defined by FT50F001 with the same frequency as for minor edit during execution of a THYDE-P run.
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9. STATUS
Package ID Status date Status
NEA-0779/02 27-FEB-1989 tested vectorized
NEA-0779/03 16-MAY-2001 Masterfiled Arrived
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10. REFERENCES

- Y. ASAHI et al.
  "THYDE-W: RCS (Reactor Coolant System) Analysis Code"
  JAERI-M 90-192, October 1990
NEA-0779/02, included references:
- T. Shimizu and Y. Asahi:
  A Through Calculation of 1,100 MWe PWR Large Break LOCA by THYDE-P
  (Sample Calculation Run 20).  JAERI-M 9819  (November 1981)
- M. Hirano:
  Through Analysis of LOFT L2-3 by THYDE-P Code (Sample Calculation
  Run 40).  JAERI-M 9765  (October 1981)
- M. Hirano and Y. Asahi:
  Through Analysis of LOFT L2-2 by THYDE-P Code (I) (Sample
  Calculation Run 30).  JAERI-M 9535  (June 1981)
- M. Hirano, T. Shimizu and Y. Asahi:
  Analysis of LOFT Small Break Experiment L3-1 with THYDE-P Code
  (CSNI International Standard Problem No. 9 and THYDE-P Sample
  Calculation Run 50).  JAERI-M 82-008  (February 1982)
- Y. Asahi, M. Hirano and K. Sato:
  THYDE-P2 Code: RCS (Reactor-Coolant System) Analysis Code
  JAERI-1300 (December 1986)
NEA-0779/03, included references:
- Y. Asahi, K. Matsumoto and M. Hirano:
  THYDE-W:RCS (Reactor Coolant System) Analysis Code
  JAERI-M 90-172 (October 1990).
- Y. Asahi, I. Sugawara and T. Kobayashi:
  Conceptual Design of the Integrated Reactor with Inherent Safety
  ANS Reprint from Nuclear Technology Vol. 91 (July 1990).
- Y. Asahi, T. Watanabe and H. Wakabayashi:
  Improvement of Passive Safety of Reactors
  ANS Reprint from Nuclear Science and Engineering 96, 73-84 (1987).
- H. Wakabayashi, T. Yoshida and Y. Asahi:
  Intrinsically Safe and Economical Reactor (ISER)
  Reprint from Nuclear Engineering and Design 126 (1991) 89-103.
- T. Watanabe, Y. Asahi, M. Fujii, Y.Anoda, K. Tasaka and Y. Kukita:
  Transient Analysis of Loss of Feed Water at Pius Experimental
  Apparatus
  The 1st JSME/ASME Joint International Conference on Nuclear
   Engineering, Vol. 1 (November 4-7 1991).
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11. MACHINE REQUIREMENTS

THYDE-P: 1160K Bytes of main storage on IBM 3081. THYDE-W: 4756K bytes for a simulation of the nuclear steam supply system of a 4-loop PWR.
NEA-0779/02
The test case ran on an IBM 3090 in 1840K bytes of main storage.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0779/02 FORTRAN-77
NEA-0779/03 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

THYDE-P2: OS370/081 VS2 03.8G. THYDE-W: FACOM OS IV/F4 MSP.
NEA-0779/02
MVS/XA (IBM 3090).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

Yoshiro ASAHI
Division of Reactor Safety Evaluation
JAERI
Tokai mura, Naka gun, Ibaraki ken
Japan
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16. MATERIAL AVAILABLE
NEA-0779/03
test-case data   mag tapeSTEAM.CLIST (STMFILE)                      DATTP
test-case data   mag tapeSTEAM.CLIST (STMHW)                        DATTP
test-case data   mag tapeSTEAM.CLIST (STMLWHP)                      DATTP
test-case data   mag tapeSTEAM.CLIST (STMLWLP)                      DATTP
test-case data   mag tapeSTEAM.CLIST (STMORIHW)                     DATTP
test-case data   mag tapeSTEAM.CLIST (STMORIHP)                     DATTP
test-case data   mag tapeSTEAM.CLIST (STMORILP)                     DATTP
source program   mag tapeA.V5L7.STEAM.FORT77                        SRCTP
test-case data   mag tapeSTMINPUT.DATA (STMORIHW)                   DATTP
test-case data   mag tapeSTMINPUT.DATA (STMTBLHP)                   DATTP
test-case data   mag tapeSTMINPUT.DATA (STMTBLLT)                   DATTP
test-case data   mag tapeJCL.CNT (LKEDTHYD)                         DATTP
test-case data   mag tapeJCL.CNT (GO)                               DATTP
test-case data   mag tapeJCL.CNT (LKEDPLOT)                         DATTP
test-case data   mag tapeJCL.CNT (PLOT)                             DATTP
test-case data   mag tapeJCL.CNT (ATF)                              DATTP
source program   mag tapeA.SV05L07.FORT77                           SRCTP
source program   mag tapeA.V5L7.INC.FORT77                          SRCTP
source program   mag tapeA.V5L7.PLOT.FORT77                         SRCTP
test-case data   mag tapeRUNDATA.DATA (CRP)                         DATTP
test-case data   mag tapeRUNDATA.DATA (HP)                          DATTP
test-case data   mag tapeRUNDATA.DATA (IRIS)                        DATTP
test-case data   mag tapeRUNDATA.DATA (ISER)                        DATTP
test-case data   mag tapeRUNDATA.DATA (PIUSEX)                      DATTP
test-case data   mag tapeRUNDATA.DATA (SPLITDC)                     DATTP
test-case output mag tapeOUTPUT--(CRP.OUT)                          OUTTP
test-case output mag tapeOUTPUT--(HP.OUT)                           OUTTP
test-case output mag tapeOUTPUT--(IRIS.OUT)                         OUTTP
test-case output mag tapeOUTPUT--(ISER.OUT)                         OUTTP
test-case output mag tapeOUTPUT--(PIUSEX.OUT)                       OUTTP
test-case output mag tapeOUTPUT--(SPLITDC.OUT)                      OUTTP
test-case data   mag tapeTEXT (1)                                   DATTP
test-case data   mag tapeTEXT (2)                                   DATTP
report                   JAERI - M 90-172 (October 1990)            REPPT
paper                    ANS Reprint Vol. 91 (July 1990)            PAPPT
paper                    ANS Reprint 96, 73-84 (1987)               PAPPT
paper                    Reprint from Nucl.Eng.&Des. 126 (1991)     PAPPT
paper                    JSME/ASME Vol. 1 (November 4-7 1991)       PAPPT
NEA-0779/02
File name File description Records
NEA0779_02.001 INFORMATION FILE 204
NEA0779_02.002 THYDE FORTRAN SOURCE FILE 1 14652
NEA0779_02.003 THYDE FORTRAN SOURCE FILE 2 14032
NEA0779_02.004 THYDE FORTRAN SOURCE FILE 3 14307
NEA0779_02.005 THYDE FORTRAN SOURCE FILE 4 1359
NEA0779_02.006 INCLUDE FILE IN IEBUPDTE FORMAT 430
NEA0779_02.007 FORTRAN LIBCONV SOURCE 15
NEA0779_02.008 STEAM-TABLE IN BCD FORMAT 3140
NEA0779_02.009 INPUT DATA V4L8A 725
NEA0779_02.010 RESTART INPUT DATA 83
NEA0779_02.011 JCL USED IN TESTING 262
NEA0779_02.012 FT06 TEST OUTPUT 628
NEA0779_02.013 FT08 TEST OUTPUT 1551
NEA0779_02.014 FT06 ORIGINAL OUTPUT 231
NEA0779_02.015 FT08 ORIGINAL OUTPUT 2046
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: blowdown, hydraulics, loss-of-coolant accident, pwr reactors.