ML19261B714

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Forwards Comments on ANS-5.4 Fission Gas Release Model. Includes Comments Re Burnup & temp-feedback Effects
ML19261B714
Person / Time
Issue date: 01/30/1979
From: Meyer R
Office of Nuclear Reactor Regulation
To: Beyer C, Buescher B, Klotz R
BABCOCK & WILCOX CO., EECCOM, HANFORD ENGINEERING DEVELOPMENT LABORATORY
Shared Package
ML19261B715 List:
References
ANS-5.4, NUDOCS 7902280542
Download: ML19261B714 (3)


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COMMITTEE CORRESPONDENCE

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AGEND A ITEM:

JAN 3 01979 FILE NO.: N/A DATE:

TO:

C. E. Beyer L. D. Noble Westinghouse Hanford A/59 General Electric Company, M/C 138 Hanford Engineering Development Lab.

175 Curtner Avenue P. O. Box 1260 San Jose, California 95125 Richland, Washington 99352 M. J. F. Notley B. J. Buescher Atomic Energy of Canada, Ltd.

The Babcock & Wilcox Company Chalk River, Ontario P. O. Box 1260 Canada, K0J1J0 Lynchburg, Virginia 24505 Chang S. Rim R. J. Klotz Korea Atomic Energy Research Institute Department 9492 P. O. Box 7, Cheong Ryang Combustion Engineering, Inc.

Seoul, Korea Windsor, Connecticut 07085 R. L. Ritzman R. A. Lorenz Science Applications, Inc.

Oak Ridge National Laboratory 2680 Hanover Street P. 0. Box X-Palo Alto, California 94304 Oak Ridge, Tennessee S. E. Turner W. Leech Southern Science Applications, Inc.

Nuclear Fuel Division,-W Corp.

P. O. Box 10 P. 0. Box 355 Dunedin, Florida 33528 Pittsburgh, Pennsylvania 15230 O

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JAN 3 01979 Enclosed is a copy of a letter from Terry Oldberg of EPRI who offers a number of comments on our ANS-5.4 fission gas release model.

I am distributirig this letter along with a few comments from John Voglewede of the Reactor Fuels Section:

1.

The discussion of a burnup dependence applied to the Booth diffusion sphere radius as opposed to the diffusivity appears to be a valid one. The Working Group may wish to discuss this point at its next meeting.

2.

Because of che distribution restrictions on Franklin's paper, we are unable to provide the group with this attachment to Oldberg's letter.

The results of the analysis do not support a strong burn-up dependence of fission gas re-lease. However. Franklin states that "the limitation of the data base prevent any clear statements on the effect of burnup."

3.

The burnup and temperature-feedback effects may indeed be difficult to distinguish for some fuel designs. This is particularly true for rods with large densification and gap size variation, as was the case for the Maine Yankee rods. Since we have not had an opportunity to examine the COMETHE code, we cannot comment on the applicability of its gas release model to this problem.

I trust you will find these comments of interest.

Sincerely,

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Ralph 0. Meyer, eader Reactor Fuels Section Core Performance Branch Division of Systems Safety

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Enclosure:

As stated O

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K. Kniel G. Marino W. Johnston J. Voglewede P. Check NRC PDR C. Hann, PNL F. Panisko, INEL J.

Dearien,

INEL R. Mason, INEL G. Owsley, EXXON M. Remley, Al M. Weber, ANS T. Oldberg, EPRI A. Roberts, EPRI

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