ML20002A932
| ML20002A932 | |
| Person / Time | |
|---|---|
| Issue date: | 11/12/1980 |
| From: | Lois L Office of Nuclear Reactor Regulation |
| To: | Johnston W Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8012090198 | |
| Download: ML20002A932 (6) | |
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NUCLEAR REGULATC.iY COMMISSION 5
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d' 1 ' 550 MEMORANCUM FOR:
W. V. Johnston, Chief, Core Perfomance Branch, DSI FROM:
Lambros lois, Reactor Physics Section, Core Performance Branch, DSI THRU:
D. Fieno, Section Leader, Reactor Physics Section, CPB, DSI
SUBJECT:
ARMP, USER'S MEETING REPORT t
A two-day meeting (Oct. 28-29,1980) was held in Dallas, Texas to discuss utility, a
EPRI and their contractor's progress and experience in the ARMP system of codes.
This was the seventh semiannual meeting held for and by APJ1P users. The meetings are organized by EPRI and this particular one has been hosted by " Texas Utilities Services, Inc." The meeting was attended by about 55 users; the agenda is in.
I found the meeting very useful in spite of a few disappointing presentations.
Of particular interest were the presentations which are related to our current review effort and the work we sponsor at BNL, for example:
the presentation by Richard Cheng of Middle South Utilities discussed the a.
ANO-1, -2 physics topical; b.
the presentation of D. VerPlanck of Yankee Atomic Electric Co. on 3'clR modeling (under contract to EPRI) and the presentation of G. Lanning of the Nebraska Public Power Co. on the COPHIN c.
impiementa tion.
BNL was represented in the meeting by D. Cokinos and L. Eisenhart.
1 A brief abstract of each of the presentations is given in Attachment 2.
Attach-ments 3-15 contain the material distributed by the speakers which includes more detailed information on each presentation.
W W kN i
Lambros Lois Reactor Physics Section Core Performance Branch Division of Systems Integration Attachments:
As stated l
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i ATTACHMENT 2 Brief Description of the Presentation in the Seventh ARMP Semiannual User's Meeting 1.
BWR Modeling, Part I - Dave VerPlanck, Yankee Atomic i
The work presented by VerPlanck has been comissioned by EPRI and is an i
extensive comparison of PDQ and CASM0, SIMULATE results. Extensive use j
was made of Vemont Yankee measurements of the earlier loadings. The calculations indicated that very good agreement can be obtained if thermal leakage correction factors and albedo corrections for corner assemblies are applied. Extensive comparisons are shown in Attachment 3.
2.
The SPEAR Code - T. Oldberg, EPRI The SPEAR code aims to optimize the operation of BWRs and minimize the estimated 3.l*. capacity factor loss due to fuel ramp rate restrictions. This is to be accomplished by applying statistical decision theory. The speaker claimed that $160 million can be earned each year if the results of the SPEAR code are applied by the utilities. The code is based on results and theory presented in the report EPRI NP-1378, " SPEAR Fuel Reliability Code System."
A copy of this report is available at the undersigner's desk. The final version of the code will be available to the utilities in early 1981. The viewgraphs of this presentation are shown in Attachment 4.
3.
Transient Analysis Using the RlENA Code - Lars Moberg, Scandpower for Carolina Power and Light This presentation dealt with the application of the RAMONA-III code to BWR transients. The RAMONA-III code uses a 3-dimensional nodal model (PRESTO) based on a 2-group time-dependent diffusion equations with 6 delayed groups.
The thermal-hydraulics are based on non-equilibrium themodynamics using the integrated momentum approach. The fuel thermodynamics and heat transfer uses radial heat conduction through fuel pellets, gap and cladding. The rest of the plant is represented by appropriate boundary conditions. The results of the application showed excellent agreement with experimental measurements.
The RAMONA-III code can handle 3-dimensional dependent problems as, for example, rod drop transients which would be difficult to handle otherwise.
The viewgraphs of this presentation are in Attachment 5.
4.
Power Shape Monitoring System y-Scan Verification of BUR Albedo Boundary, Conditions and Spectrum Correction Factors - T. Ancona, NAI The purpose of this work was to determine boundary conditions which could improve BWR representation.
It was found that beyond the proper value of the albedo one must use the proper value of the " spectrum correction factor."
Power distribution and control rod worth improved significantly. The work is not completed yet and no handouts were circulated.
5.
Physics Topical ANO-1, Richard Cheng, Middle South Utilities A brief description of the physics topical report which has been submitted to the NRC for review was discussed. The viewgraphs were pages of the report.
It was stated that due to the delay caused by the -(well publicized) clams r..
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in the cooling water, refueling will not take place until June 1981. The cover letter on the topical requested review to accomodate an April 1981 refueling.
6.
COPHIN Implementation Experience - Gene Lanning, Nebraska Public Power The purpose of the COPHIN code is to interface PCQ to CPM and/or the CASMO programs. This program will automate microscopic depletion updating. The running of the program uses very little CPU time but greatly facilitates running P00 by preparing the input automatically.
Control rods have to be input manually. The COPHIN code has been received by BNL and will be implemented. The presentation handout is shown as Attachment 6.
7.
Monticello Succorting Calculations - Cliff Bonneau, Northern States Power Co.
Many older experimental data have been analyzed with the ARMP system codes.
The purpose was to update the computational capabilities for future predictive refueling calculations.
8.
IBM and CDC Versions of Predictor-Corrector in PDQ - George Poetschat, GRP Consulting, Inc.
The purpose of the predictor-corrector technique applied to P0Q is to cut down on the running time by improving on the convergence, lowering the number of iterations. The results showed that the number of iterations can be cut by a factor of 3-5, but the computation time savings are not as big due to increased calculations per iteration. A brief description is given in Attachment 7.
9.
PWR Nodal Code Models and hnorovements - Eddie Liang, Portland General Electric The purpose of this work was to improve the N00E-P, a 3-dinensional nadal code.
To this end, data from Trojan have~ been used along with PDQ comparisons. The areas where improvements have been affected include the source term, diffusion area or a function of exposure, the treatment of the albedo and others. A comparison of the improved NODE-P with direct instrument measurements at Trojan show good to excellent agreement. The handout which includes extensive PDQ and experiment comparisons is shown as Attachment 8.
- 10. SWR Modeling: Part II - Dave VerPlanck, Yankee Atomic Electric Co.
l This is the second part of the presentation described in 1 above. An extensive description was given of the Vennont Yankee Cycles 1-5.
The results showed that with the proper emoirical factors, excellent agreement wi th experiment can be obtained. Tables of comparison are shown in Attachment 9.
- 11. McGuire P00 Power Distribution - Quang Huyuh, Duke Power Co.
The purpose of this work was to calculate the depletion characteristics of McGuire 1 Cycle 1.
This reactor is a Westinghouse PWR built by Duke Power Co. The main interest focused on the initial boron concentration and the power distribution as a function of burnup. The codes used were EPRI-CELL,
. NUPUNCHER, EPRI-CPM and PDQ7. A difference of 30-70 ppm in critical boron concentration between this calculation and the vendor data was identified.
No explanation was offered for the difference. The comparison and the main results of the calculations are shown in Attachment 10.
- 12. BWR Model Develocment at Carolina Power and Licht - Paul Sieh, C.P. and L.
The purpose of this work is to prepare the C.P. and L. staff to perform cycle management analysis by 1982. To this end extensive benchmarking and analytic method error determination is done using the data available from the Brunswick plant operations. The analytical scheme constructed using existing codes and a limited number of comparisons are shown in Attachment 11.
- 13. SIMULATE Comoarisons with 3-0 PDQ - T. Ancona, NAI This was a presentation of partial results of ongoing work of SIMULATE and PDQ comparisons. The tentative conclusion was that for good Keff and power distribution prediction in BURS, good values of the albedo and the spectral correction factor must be used. No written material was distributed.
- 14. PSEUDAX Development - Burt Rothleder, SAI The objective of this work is to develop a code which will cut computation time in depletion calculations. To this end g factors are computed for cross section adjustment using HARMONY. Results up to now showed that the scheme does not work effectively. It was attributed to an EPRI-N0DE-P misnormalization. No written material was distributed.
- 15. Comoarison of SIMULATE, PRESTO and CDMT in Predicting Goerational Data - Ron Lucier, Yankee Atomic Electric Co.
The purpose af this effort was to identify the source of differences in opera-tional data from different codes.
It was found that PRESTO contains errors.
It was thought though that it is worth maintaining. No written material was distributed.
- 16. PDQ-8 and Other PD0 Developments - George Poetschat, GRP Consulting, Inc.
The PDQ-8 version has been released to the National Energy Sof tware Center in 1979; however, it is not operational yet. The program is restricted to U. S.
users. The manual has been completed; the code is written for the CDC 7600 and 6600. The P00-8 is based on a Bettis Atomic Power Laboratory report, WAPD-TM-1266 May 1978. Some of the main features of the new code are:
(a) Block depletion, to cut down running time; (b) Skewed lines, for more accurate geometry description; and (c) expanded edit capability.
A brief description of the program features are shown in Attachment 12.
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- 17. CASMO-Based Signal to Power Calculations - Glen Horne, Duke Power Co.
4 The purpose of this work was to improve the signal to power conversion using the CASMO code for the Self-Powered Neutron Detectors used in Oconee. The signals of the detectors are adjusted for burnup, boron, etc., and it is intended to update the plant computer. The results were compared with the B&W results with excellent agreement. A more extensive description of the scneme and the comparisons are shown in Attachment 13.
- 18. BOL Comoarisons of CPM and CASMO with Monte Carlo - Bill Moore, Washington Public Fower The Exxon XMC Monte Carlo code was used to evaluate the CPM and the CASMO codes both for BWR and PWR assemblies. The library of XMC is difficult to trace; the initial was from BHWL, but modifications have been effected.
K., epithermal multiplication, epithermal escape probabilities, thermal multiplications and power distributions are compared for Quad Cities fuel type la. Attachment 14 shows that the comparisons are very good. An ANS abstract has been published in June 1980 by Duane Tompson.
- 19. NORGE Modifications - Glen Correll, WPPSS l
The purpose of the NORGE modifications was to enable treatment of Samarium microscopic cross sections, direct restart capability, exact values of V:f 4
ano KIf and improved input and output formats. Comparisons of NORGE to SIMULATE are shown in Attachment 15.
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W MEETING
SUMMARY
DISTRIBUTION CORE PERFCR4ANCE BRANCH Central File w/ attachment 2 Principal Staff Particioants M
L. Lots NRR R/F w/ attachment 2 CPB R/F w/ attachment 2 H. Denton no attachment E. Case NRR-PPAS D. Ross w/ attachment 2 L. Rubenstein w/attacnment 2 W. Johnston W. Butler J. Stolz P. Check W. Krecer D. Eisenhut F. Schrceder R. Vollmer
- 5. Hanauer IE (3)
ACRS (16)
R. Meyer L. Phillips D. Fieno With attachments Reactor Physics Section, CPB w/ attachment 2