Computer Programs
NESC0818 CONTEMPT-4/MOD5&6.
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NESC0818 CONTEMPT-4/MOD5&6.

CONTEMPT-4/MOD5&6, LWR Containment Long-Term Pressure Distribution and Temperature Distribution in LOCA

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1. NAME OR DESIGNATION OF PROGRAM

CONTEMPT-4MOD5, CONTEMPT4/MOD6

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2. COMPUTERS

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Program name Package id Status Status date
CONTEMPT4/MOD6 NESC0818/07 Arrived 19-JUN-2002

Machines used:

Package ID Orig. computer Test computer
NESC0818/07 CRAY 1
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3. DESCRIPTION OF PROGRAM OR FUNCTION

CONTEMPT-4/MOD5 describes the response of multicompartment containment systems subjected to postulated loss-of-coolant accident (LOCA) conditions. The program can accommodate both pressurized water reactor (PWR) and boiling water reactor (BWR) containment systems. Also, both design basis accident (DBA) and degraded core type LOCA conditions can be analyzed. The program calculates the time variation of compartment pressures, temperatures, and mass and energy inventories due to intercompartment mass and energy exchange taking into account user-supplied descriptions of compartments, intercompartment junction flow areas, LOCA source terms, and user-selected problem features. Analytical models available to describe containment systems include models for containment fans and pumps, cooling sprays, heat conducting structures, sump drains, PWR ice condensers, and BWR pressure suppression systems. To accommodate degraded core type accidents, analytical models for hydrogen combustion within compartments and energy transfer due to gas radiation are also provided.

 

CONTEMPT4/MOD6 is an update of previous CONTEMPT4 versions. Improvements in CONTEMPT4/MOD6 over CONTEMPT4/MOD3 include coding of a BWR pressure suppression system model, a hydrogen/carbon monoxide burn model, a gas radiation heat transfer model, a user specified variable junction (leakage) area as a function of pressure or time, additional heat transfer coefficient options for heat structures, generalized initial compartment conditions for inerted containment, an alternative containment spray model and spray carry-over capability. Also, the thermodynamic properties rountines have been extended to accomodate the higher temperature and multicomponent gas mixtures associated with combustion. In addition, reduced running time is achieved by incorporation of an optional implicit numerical algorithm for junction flow. This makes economically feasible the analysis of very long term transients such as are encountered during degraded core accidents with hydrogen combustion. The user has the option of turning off the implicit routine through user input, if desired.

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4. METHODS

Containment thermodynamic conditions of hydrogen/air/steam/liquid water mixtures are determined by using modularized equation-of-state subroutines and tabulated water properties. The numerics in the code are completely explicit except for the predictor-corrector technique used to estimate the heat structure effects on compartment conditions, an implicit calculation of junction flow with inertia, and an optional implicit routine for junction flow calculation approaching pressure equilibrium.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Maxima of

  • 999 lumped parameter compartments

  • 99 heat conducting structures using a variety of heat transfer

  • options and boundary conditions.

 

Intercompartment flow junctions may be calculated for either a sharp-edge orifice (single phase homogeneous or two-phase flow) or a nozzle (vapor flow only). Containment cooling spray analytical models are provided for either single or double heat exchangers.

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6. TYPICAL RUNNING TIME

The long-term BWR sample problem with hydrogen burn requires approximately 9.5 minutes on a CDC CYBER175 and 4.5 hours on an IBM4331, and the ice condenser sample problem requires about 9 seconds on a CDC CYBER170/875 and 5.6 minutes on an IBM4331.

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7. UNUSUAL FEATURES OF THE PROGRAM

The architecture of CONTEMPT-4/MOD5 is completely modular. Dynamic storage allocation coding, optional automatic time-step control, optimal specification of input data, and a restart capability permit flexible use of the available program features.

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8. RELATED OR AUXILIARY PROGRAMS

The CONTEMP-4/MOD5 code is the most recent in the CONTEMPT series of programs originally developed at EG>G Idaho, Inc. While it does not replace CONTEMPT-LT/028 (NESC 433), CONTEMPT4/MOD5 can perform simplified boiling water reactor (BWR) containment studies. CONTEMPT4/MOD5 is an improvement to CONTEMPT4/MOD4 for ice containment analysis. STH20G generates the water properties library used by CONTEMPT4, and PLOTCT44 plots the values of variables calculated by CONTEMPT4. PLOTCT44 is not available in the IBM version.

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9. STATUS
Package ID Status date Status
NESC0818/07 19-JUN-2002 Masterfiled Arrived
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10. REFERENCES
NESC0818/07, included references:
- C.C. Lin, C. Economos, J.R. Lehner, G. Maise:
CONTEMPT4/MOD6 - A Multicompartment Containment System Analysis Program
NUREG/CR-4547 (BNL-NUREG-51966 (March 1986).
- M. Birgersson:
CONTEMPT4/MOD6 CRAY Version Tape Description, Implementation Information
NESC Note 90-38 (January 19, 1990).
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11. HARDWARE REQUIREMENTS

60,000 (octal) words of small core memory (SCM) and 220,000 (octal) words of large core memory (LCM) are required on a CDC CYBER176. 160,000 (octal) words of SCM are required on a CDC CYBER170/875. CalComp or FR80 plotting devices are needed for graphical output. 1150K bytes of memory are required on an IBM4331.

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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC0818/07 FORTRAN
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13. SOFTWARE REQUIREMENTS

SCOPE 2.1 (CDC 7600), NOS/BE (CDC CYBER 176) NOS 2.2 (CDC CYBER175,170/875), MVS (IBM3090), VM/CMS (IBM4331).

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

CONTEMPT4 cannot be compiled successfully using the FTN5 compiler. CONTEMPT4, STH20G, and PLOTCT44 will not load with the NOS1.5-564 or 587 loader; NESC used the NOS1.5-552 loader on a CDC CYBER175.

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15. NAME AND ESTABLISHMENT OF AUTHORS

7600

C.C. Lin, C. Economos, J.R. Lehner, G. Maise, and K.K. Ng

Department of Nuclear Energy

Brookhaven National Laboratory

Upton, New York 11973, USA

 

3090

S.M. Mirsky

Baltimore Gas and Electric, USA

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16. MATERIAL AVAILABLE
NESC0818/07
CONTEMPT4 Update Source
EG&G Environmental Routines UPDATE Source
HEADER Routines UPDATE Source
German Stand. Probl. on D-15, BL-MD S.P.
CVTR Test 3 Sample Problem Input
HDR V-21 Sample Problem Input
Typical PWR Application Input
Ice Condenser (modified) S.P. Input
BWR Mark III SBA Case H2-Burn S.P. Input
German Stand. Probl. on D-15, BL-MD S.P.
CVTR Test 3 Sample Problem Output
HDR V-21 Sample Problem Output
Typical PWR Application Output
Ice Condenser (modified) S.P. Output
BWR Mark III SBA Case H2-Burn S.P. Output
Sample Control Information
NUREG/CR-4547 BNL-NUREG-51966 (March 1986)
NESC Note 90-38 (January 19, 1990)
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: BWR reactors, accidents, containment, energy transfer, ice condensers, mass transfer, pressure, pwr reactors, reactor safety, temperature distribution.