March 22nd, 2011 – Sandia not likely to assist Oak Ridge with actual Fukushima data

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From: Gauntt, Randall 0 [[email protected]]
Sent: Tuesday, March 22, 2011 7:42 PM
To: Humphries, Larry Laron
Cc: Pickering, Susan Y; Orrell, Stanley A; Tinkler, Charles; Lee, Richard
Subject: RE:

Short answer is – we are not likely to hand over models to ORNL. Between you and me, a large reason is that they will try to run the models and either a) have a lot of instructional and explainational questions requiring our nursing, b) have no end of questions on the code predictions and why, or c) generate public issues potentially in contrast with our ongoing work requiring our energy to explain the differences. All dilute our limited resources to respond to an unacceptable level.

This is the reality – in addition to the fact that we don’t want our work over the past 10 years to be credited to ORNL.

You could conver to Juan that Sandia maintains tight configuration control over the decks and cannot disperse decks without NRC direction and participation. Prioliferation of decks, even within our own ranks, has to be managed. Plus, all of the pragmatic reasons cited above. None of this would seem reasonable to ORNL, and I don’t know how to respond aside from ignoring the requests mainly due to distraction.


From: Humphries, Larry Laron
Sent: Tuesday, March 22, 2011 3:52 PM
To: Gauntt, Randall 0
Subject: FW:

Perhaps you can help Juan or if you like, refer him to Wagner.


From: Carbajo, Juan 3. []
Sent: Saturday, March 19, 2011 12:22 PM
To: Humphries, Larry Laron

Hi Larry,

It has been some time since we communicated, after my trip to SNL last January.

I was waiting for the advice of Randy Cole on modeling the split of blowdown stream into water and steam.

I am contacting you this time to ask you for a different favor.

We know here at ORNL that SNL has been involved in MELCOR calculations for the Fukushima reactor, in particular for the spent fuel pool of Unit 4.

I am sure you know all of this work.

We are here also doing some work for the Japanese reactors.

Will it be possible to get the actual dimensions of the pool of that reactor? And the fuel heat load?

Do you have a MELCOR model of the spent fuel in the pool?

Thanks and best regards.

Juan J. Carbajo
Oak Ridge National Laboratory

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