ML20093N081
| ML20093N081 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 10/19/1984 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20093N062 | List: |
| References | |
| DPC-NF-2010-APP, DPC-NF-2010-APP-A, NUDOCS 8410310359 | |
| Download: ML20093N081 (6) | |
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Appendix A Code Summary 8410310359 841019 PDR ADOCK 05000369 A-1 P
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CASMO-2 CASNO-2 'is a multi group two-dimensional transport theory code for burnup cal-culations on BWR and PWR assemblies. This code has been developed by Studsvick Energiteknik AB and supported by EPRI.
CHART CHART prepares' cross section tables in HARMONY format from cross section data producea by CASHO-2. CHART reduces significant.ly the tedious task of hand transferring values from CASMO-2 printout to macroscopic and microscopic tables
'in card image HARMONY format.
Two, three, and four group cross section data
-may be obtained with one-dimensional HARMONY interpolating tables.
COMETHE-III-J The COMETHE code calculates fuel pin thermal and mechanical behavior as a func-
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tion of burnup. 'This code was developed by Belgo Nucleaire and licensed in this country by the S. M. Stoller Corp. EPRI is sponsoring the distribution and further development of this code for the utilities. The code does all the calculations describad for TAFY and includes a relocation and cracking model to determine fuel-clad interaction forces.
CORE CORE (Codes for Operating Reactor Evaluation) is a package of computer routines for the off-line evaluation of. reactor performance. CORE uses as input:
detailed reactor physics data, isotopics, and thermal-hydraulics data.
Calcu lated values are:
F,FAH, assembly burnups, isotopics, reactivity, and core q
thermal-hydraulics information.
DELAY DELAY calculates core averaged delayed neutron fractions for six energy groups,
. core averaged decay _ constants for six energy groups, core averaged delayed neu-tron fraction with and without importance factor, estimated prompt neutron A-2
i as:
J h
.s:
K lifetime, and reactivity versus period.
Input consists primarily of isotopic h
fission fractions versus burnup and enrichment from PDQ$7 calculations.
p E /s-h-
- EPRI-CELL EPRI-CELL computes the space, energy and burnup dependence of the neutron spec-
.trum within cylindrical cells.of Light Water Reactor fuel. rods.
Its primary
-out'putLconsists of broad group, microscopic, exposure dependent cross sections for subsequent use in multidimensional diffusion theory depletion analysis.
- EPR1-CELL utilizes three industry accepted subcodes; GAM-1, THERMOS, and CINDER.
l-EPRI-CPM.
- EPRI-CPM is a multi-group two-dimensional collision probability code for burnup I
calculations on BWR and PWR assemblies. The code handles a-geometry consisting of cylindrical fuel rods-of varying composition in a square pitch array with callowance for fuel rods loaded with gadolinium, burnable absorber-rods,. cluster control rods,,in-core instrument channels, water gaps, boron steel curtains and cruciform control. rods in the-regions sep ating fuel-assemblies.
EPRI-FIT EPRI-FIT is~a program which processes the PDQ$7 integral file and calculates-and edits values needed by the EPRI-NODE code. EPRI-FIT greatly reduces the hand calculation time needed to extract these values from the PDQ$7 printout
.and improves the quality' assurance. A data file under the locai name of COLOR is written which contains the EPRI-FIT edited data and is used as input to the
- SUPERLINK prograu.
EPRI-NODE t-L EPRI-NODE is a multi-dimensional nodal code derived from to FLARE. The
.EPRI-NODE program computes the core effective multiplication factor, the three-dimensional' core power distribution, core coolant flow and temperature distribution, and fuel exposure'distribt ion. The program includes the effects of partially ~ inserted full-length control rods,'part-length rods, and up to 13 A-3
'different fuel assembly types.with different enrichments and burnable absorber shim loadings. EPRI-NODE has a capacity to represent the core with 32 axial nodes for'each fuel assembly and 30x30 nodes in the XY plane.
- The program iterates to account for the interaction between power distribution and core nuclear. properties which depend on coolant flow and coolant tempera-
'ture distributions, fuel temperature distribution and xenon distribution. The program computes the time dependence of xenon following changes in power level and/orl changes-in power distribution. The program permits fuel shuffling from one -location to another and fresh fuel insertion for burnup cycle calculations.
Individual steps can by stacked for either xenon transient or fuel cycle burnup calculations.
EPRI-NUPUNCHER NUPUNCHER prepares cross section tables in HARMONY format from cross section data produced by EPRI-CELL and placed on the ECDATA file.
NUPUNCHER reduces ~
significantly the tedious task of hand transferring values from the EPRI-CELL printout 'to macroscopic and microscopic tables in card image HARMONY format.
Two, three'and four group cross section data may be obtained with one-dimen-sional HARMONY interpolating tables.
EPRI-PDQ97 MODIFICATIONS PDQ97 is the industry accepted multi group one, two, or three-dimensional dif-fusion depletion code. EPRI-ARMP uses PDQ97/ Version II with minor modifica-tions to allow options for improved removal treatment, peak power editing, and re-editing.
EPRI-SHUFFLE The EPRI-SHUFFLE program will read a PDQ97 concentration file, make certain modifications to this file, and write a new updated concentration file. This
- procedure is accomplished by defining " assembly regions" in the program input.
Assembly' regions are square arrays of mesh points containing depletable nuclide concentrations and superimposed on the original PDQ97 geometry. These assembly
'A-4
y -m t
e
' regions are then used to describe the movement'of existing nuclide.concentra-tions by translation,-reflection and/or rotatioa.
In addition, new fuel concentrations'can replace spent fuel concentrations in selected assembly iregions described in the program's-input.
-EPRI-SUPERLINK s
SUPERLINK accesses data on the files produced by EPRI-FIT and, together with relevant input information for tile management and for data processing control,
- produces polynomial coefficients for use in EPRI-NODE.
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MULTIFIT' JMULTIFIT reads EPRI-CELL cross section-files and generates HARMONY-cross sec-tions and : g-factors. Both HARMONY masks and function tables can include the effects of up'to three independent variables. MULTIFIT can perform almost all of the functions of EPRI-NUPUNCHER.
PDQ97 See EPRI-PDQ67 Modifications.
NODE UTILITY CODE (NUC)
The NUC program is a. package of subroutines that performs any necessary utility function to EPRI-NODE files. The major subroutines are:
I ~ FILE - this mode lists, merges, purges, addr, rearranges, edits, etc..the NODE cases on one or more history. files.
l II.
FLEX - this mode takes an existing file, expands or collapses it to a new problem size, and then stores it on a new disk.
.III.
COPY this mode copies a given history file from disk storage (working file) to magnetic tape storage (permanent backup file) and vice versa.-
L_
A-5 k
V
- 7
,.s IIV.
NAkGINS - this mode performs those operations which are necessary to cal-
= file (s). It 'also plots the results in the form of a " fly speck". graph.
TACO 2 TACO 2 conservatively predicts fuel pin temperature and fuel pin pressure.
It includes'models for fuel densification, fuel swelling, fuel restructuring, gas release,' cladding creep, and gap closure.
VIPRE VIPRE is a transient and steady state open channel thermal hydraulic code that considers energy mixing between channels and is used to calculate flow distribu-tion among individual channels in an assembly or a cluster of fuel pins.
It calculates flow,~ pressure drop, coolant parameters up the: channel, and DNBR.
TACO-
~ TACO conservatively predicts fuel pin temperature and fuel pin pressure.
It
. includes models for fuel densification, fuel. swelling, fuel restructuring, gas release,. cladding. creep, and gap closure.
o
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