NESC0780 NALAP
NALAP, Thermohydraulics for Na Cooled LMFBR after Pipe Rupture and Accidents
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 AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| NALAP | NESC0780/01 | Tested | 24-FEB-1981 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NESC0780/01 | CDC 7600 | CDC 7600 |
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3. DESCRIPTION OF PROBLEM OR FUNCTION
NALAP is an LMFBR system
transient code. This code, adapted from the light water reactor
transient code RELAP3B, simulates thermalhydraulic response of
sodium-cooled fast breeder reactors when subjected to postulated
accidents such as a massive pipe break as well as a variety of
other upset conditions that do not disrupt the system geometry.
NALAP is an LMFBR system
transient code. This code, adapted from the light water reactor
transient code RELAP3B, simulates thermalhydraulic response of
sodium-cooled fast breeder reactors when subjected to postulated
accidents such as a massive pipe break as well as a variety of
other upset conditions that do not disrupt the system geometry.
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4. METHOD OF SOLUTION
Various components of the plant are
represented by control volumes. These control volumes are
connected by junctions, some of which may be leak or fill
junctions. The fluid flow equations are modeled as compressible,
single-stream flow with momentum flux in one dimension. The
transient response is computed by integrating the thermal-
hydraulic conservation equations from user-initialized operating
conditions by an implicit numerical scheme. The point-kinetics
approximation is used to represent the time-dependent heat
generation in the reactor core.
Various components of the plant are
represented by control volumes. These control volumes are
connected by junctions, some of which may be leak or fill
junctions. The fluid flow equations are modeled as compressible,
single-stream flow with momentum flux in one dimension. The
transient response is computed by integrating the thermal-
hydraulic conservation equations from user-initialized operating
conditions by an implicit numerical scheme. The point-kinetics
approximation is used to represent the time-dependent heat
generation in the reactor core.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
Maxima of -
40 control volumes
50 connecting junctions
6 thermal properties
25 pressures
13 liquid temperatures per pressure
6 gas temperatures per pressure
Pressure table values must be greater than zero and less than or
equal to 7000 psia. The pressure table restrictions may be
altered by modifying DIMENSION statements.
Maxima of -
40 control volumes
50 connecting junctions
6 thermal properties
25 pressures
13 liquid temperatures per pressure
6 gas temperatures per pressure
Pressure table values must be greater than zero and less than or
equal to 7000 psia. The pressure table restrictions may be
altered by modifying DIMENSION statements.
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6. TYPICAL RUNNING TIME
A 27-volume, 32-junction problem took
approximately 32 milliseconds per time-step on a CDC7600.
Typically, the time-step for a double-ended pipe break case was
0.05 millisecond near the break time. Beyond 0.3 millisecond
after the break, the time-step was increased to 0.5 millisecond.
The four sample problems were executed in 6 CP minutes on a
CDC7600.
A 27-volume, 32-junction problem took
approximately 32 milliseconds per time-step on a CDC7600.
Typically, the time-step for a double-ended pipe break case was
0.05 millisecond near the break time. Beyond 0.3 millisecond
after the break, the time-step was increased to 0.5 millisecond.
The four sample problems were executed in 6 CP minutes on a
CDC7600.
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10. REFERENCES
B. A. Martin, A. K. Agrawal, D. C. Albright, L. G.
Epel, and G. Maise, NALAP An LMFBR System Transient Code, BNL
50457, July 1975.
K. V. Moore and W. H. Rettig, A Digital Program for
Reactor Blowdown and Power Excursion Analysis, IDO-17263, March
1968.
W. H. Rettig, G. A. Jayne, K. V. Moore, C. E. Slater,
and M. L. Uptmor, RELAP3--A Computer Program for Reactor Blowdown
Analysis, IN-1321, June 1970.
B. A. Martin, A. K. Agrawal, D. C. Albright, L. G.
Epel, and G. Maise, NALAP An LMFBR System Transient Code, BNL
50457, July 1975.
K. V. Moore and W. H. Rettig, A Digital Program for
Reactor Blowdown and Power Excursion Analysis, IDO-17263, March
1968.
W. H. Rettig, G. A. Jayne, K. V. Moore, C. E. Slater,
and M. L. Uptmor, RELAP3--A Computer Program for Reactor Blowdown
Analysis, IN-1321, June 1970.
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11. MACHINE REQUIREMENTS
CDC7600 (or CYBER76) with 142,000 (octal)
words of memory. In addition to card input and printer output, a
FORTRAN logical unit 1 may be used for the automatic time-step
option, and units 2, 3, and 4 may be used under the restart
option. These units may be assigned to disk or tape.
CDC7600 (or CYBER76) with 142,000 (octal)
words of memory. In addition to card input and printer output, a
FORTRAN logical unit 1 may be used for the automatic time-step
option, and units 2, 3, and 4 may be used under the restart
option. These units may be assigned to disk or tape.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
The
following non-ANSI language extensions were used:
OVERLAY statements and calls.
ENCODE and DECODE statements to prepare output page headings.
PROGRAM statements to specify file assignments.
Non-ANSI system routines called:
EOF--returns nonzero value when end-of-file reached.
REMARK--places message on DAYFILE.
DATE--returns calendar date in the form mm/dd/yy.
TIME--returns time of day in the form hh.mm.ss.
SECOND--returns CP time used.
SHIFT--performs a left or right binary shift.
If all of these are replaced by dummy routines, only the page
headings are affected. A COMPASS routine named WHEN is included
which may be removed for non-7600 environments. For restart
problems, the data is read from TAPE3 and is written to TAPE4.
The
following non-ANSI language extensions were used:
OVERLAY statements and calls.
ENCODE and DECODE statements to prepare output page headings.
PROGRAM statements to specify file assignments.
Non-ANSI system routines called:
EOF--returns nonzero value when end-of-file reached.
REMARK--places message on DAYFILE.
DATE--returns calendar date in the form mm/dd/yy.
TIME--returns time of day in the form hh.mm.ss.
SECOND--returns CP time used.
SHIFT--performs a left or right binary shift.
If all of these are replaced by dummy routines, only the page
headings are affected. A COMPASS routine named WHEN is included
which may be removed for non-7600 environments. For restart
problems, the data is read from TAPE3 and is written to TAPE4.
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NESC0780/01
| File name | File description | Records |
|---|---|---|
| NESC0780_01.001 | SOURCE PROGRAM | 23504 |
| NESC0780_01.002 | INPUT CASE 1 | 239 |
| NESC0780_01.003 | INPUT CASE 2 | 199 |
| NESC0780_01.004 | OUTPUT CASE 1 | 1787 |
| NESC0780_01.005 | OUTPUT CASE 2 | 1609 |
Keywords: LMFBR reactors, accidents, design basis accidents, fluid flow, heat transfer, hydraulics, kinetics, pipes, reactor cooling systems, ruptures, transients.