ML20148N810
| ML20148N810 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1978 |
| From: | Dunefeld M Office of Nuclear Reactor Regulation |
| To: | Kniel K Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7811270234 | |
| Download: ML20148N810 (1) | |
Text
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MEETING
SUMMARY
OCT 311978 DISTRIBUTION:
S. Hanauer R. Mattson/F. Schroeder R. Fraley, ACRS (16)
I&E(3)
J. Knight T. Novak R. Tedesco R. Denise D. Skovholt D. Vassallo E. Eisenhut B. Grimes J. Miller M. Ernst W. Ganmill V. Moore R. Vollmer R. Bernero W. Morrison C. Roberts J. Davis E. English C. Kelber L. Tong S. Weiss P. Check NRC PDR 78.112702-3 '
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j WASHINGTON, D. C. 20665 p
OCT 311978 MEMORANDUM FOR: K. Kniel, Chief, Core Performance Branch, DSS THRU: D. Fieno, Leader, Reactor Physics Section, CPB, DSS Oh FROM: M. Dunenfeld, Reactor Physics Section, CPB, DSS
SUBJECT:
ARMP USERS MEETING, OCTOBER 3 AND 4, 1978 M. Dunenfeld attended the ARMP (Advanced Recycle Methodology Program) users meeting in Westboro, Massachusetts on October 3 and 4,1978. Also in attendance were D. Diamond, J. Herczeg and D. Cokinos of BNL,~all of whom work on our Reactor Core Safety Analysis Technical Assistance Program.
A major topic discussed at the meeting was the CASMO computer program, which can be used instead of CPM in ARMP. The advantages of CASMO are that it is much easier to prepare input for than CPM, it runs much faster, and it has an automatic interface with SIMULATE, the improved nodal code which replaces EPRI-node. There is a fee of about $25,000 to obtain CASMO.
From cost savings data presented at the meeting, as a result of the first two advantages indicated above, I conclude that BNL should be allowed to purchase CASMO. Two additional things have to be done, however, before any further action is taken on this. These are: 1. BNL is preparing a definitive statement of the savings CASMO will provide, and 2. We need to explore sharing the cost with other DOE laboratories probably interested in obtaining CASMO. These are Berkeley and Argonne. ARMP is on the com-puters at these labs.
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Marvin S. Dun nfeld Reactor Physics Section Core Performance Branch Division of Systems Safety Distribution:
(Seeattached)
Conta c'.: M. Dunenfeld, NRR x27577