Spent Fuel Pool Meltdown Testing at Sandia (NRC)

Here is the link to the delayed report.  More later.


http://pbadupws.nrc.gov/docs/ML1307/ML13072A056.pdf
Following is copied from the cover:

NUREG/CR-7143   ML13072A056

SAND-2007-2270

Characterization of Thermal-Hydraulic

and Ignition Phenomena in Prototypic,

Full-Length Boiling Water Reactor Spent

Fuel Pool Assemblies After a Postulated

Complete Loss-of-Coolant Accident

Office of Nuclear Regulatory Research

Manuscript Completed: October 2012

Date Published: March 2013

Prepared by

E. R. Lindgren and S. G. Durbin

Sandia National Laboratory

Albuquerque, NM 87185

G. A. Zigh, Technical Advisor

A. Velazquez-Lozada, Project Manager

So, I have studied a lot of that report, but I still have work to do in reviewing that.  It is not quality work.  Following are selected sentences (italics) and some of my findings to date:

PAGE iii 

The close coupling of the experimental and numerical programs allowed for rapid validation and improvement of the MELCOR whole pool calculations. Because of the success of this approach, this project will be used as a model for subsequent studies.  

As I read the report, MELCOR was certainly not validated.  Data was fitted to MELCOR, but it is not proven that MELCOR would be applicable beyond the experiments that are described.  It certainly has not been established that the approach in these limited experiments is in any way suitable as a model for subsequent studies.

PAGE xix

Incorporation of “breakaway” Zircaloy oxidation kinetics into MELCOR was vital for

accurately capturing the Zircaloy heat-up to ignition and oxygen consumption.  

  
This is reported as one of several "... key findings from this integrated experimental and simulation program ... ."  Of what value has MELCOR ever been if it did not incorporate the kinetics of Zircaloy oxidation?  It appears that MELCOR has been updated based on the limited experiments, but it has not been established that this specific updating of MELCOR is of any use elsewhere.

PAGE 1

It was known that some of the assumptions in the accident progression in NUREG-1738 were necessarily conservative,especially the estimation of the fuel damage. Furthermore, the NRC desired to expand the study to include accidents in the SFPs of operating power plants. Consequently, the NRC continued SFP accident research by applying best-estimate computer codes to predict the severe accident progression following various postulated accident initiators. The best-estimate computer code studies identified various modeling and phenomenological uncertainties that prompted a need for experimental confirmation [2]. The present experimental program was undertaken to address thermal-hydraulic issues associated with complete loss-of-coolant accidents in boiling water reactor (BWR) SFPs.  

Supplementary Notes by G. A. Zigh, Technical Advisor  and

A. Velazquez-Lozada, Project Manager include:

Sandia National Laboratories (SNL) performed an experimental program to address thermal-hydraulic issues associated with compete loss-of coolant accidents in boiling water reactor spent fuel pools (SFPs).  The objective of these experiments was to provide basic thermal-hydraulic data associated with a postulated SFP complete loss-of-coolant accident.  The accident conditions of interest for the SFP were simulated in a full-scale prototypic fashion (electrically heated rods in prototypic assemblies and SFP rack) so that the experimental results closely represent actual fuel assembly responses. A major impetus for this work was to facilitate code validation (primarily MELCOR) and reduce modeling uncertainties within the code.

   

I have already posted the following on October 6, 2013, however, I am repeating that post for convenience at this entry.  This was first posted by Enformable and the following is copied from there.

March 16th, 2011 – Classified as OUO documents – BWR zirc fire data

From: Gibson, Kathy
Sent: Wednesday, March 16,2011 2:17 PM
To: Zigh, Ghani
Subject: Re: Spent Fuel Experiments

We have multiple requests from multiple parties for a plethora of information. This request is in the que. Will talk with you about this when I can.

Thanks

From: Zigh, Ghani
To: Gibson, Kathy; Scott, Michael
Sent: Wed Mar 16 14:01:31 2011
Subject: FW: Spent Fuel Experiments

What is our decision on sharing the BWR zirc fire data with GE and NEI.

They are classified as OUO documents.

From: Durbin, Samuel [mailto:sdurbinsandia.gov]
Sent: Wednesday, March 16, 2011 1:57 PM
To: Zigh, Ghani
Subject: FW: Spent Fuel Experiments

From: Saito, Earl F. (GE Power & Water) [mailto:EarI.SaitoqCanf.com1
Sent: Wednesday, March 16, 2011 11:35 AM
To: Durbin, Samuel; Rochau, Gary; Lindgren, Eric; Gauntt, Randall 0
Cc: Bonano, Evaristo Jose; Sorenson, Ken B
Subject: RE: Spent Fuel Experiments

Thanks

From: Durbin, Samuel rmailto:sdurbin0sandia.gov1
Sent: Wednesday, March 16, 2011 1:20 PM
To: Rochau, Gary; Lindgren, Eric; Gauntt, Randall 0
Cc: Saito, Earl F. (GE Power & Water); Bonano, Evaristo Jose; Sorenson, Ken B
Subject: RE: Spent Fuel Experiments

Gary,

Attached are Mhe three relevant papers that were published in the ANS Transactions - Winter Meeting 2006 I Volume 95.

Your will note that the two papers based on the Sandia testing were heavily redacted at the instruction of the NRC. The test information is generally considered Official Use Only. We will need to receive permission from the NRC to release more substantial reports.

Sam

Samuel Durbin II
Sandia National Laboratories
Advanced Nuclear Fuel Cycle Technologies, Organization 6223
PO Box 5800 - MS 0747
Albuquerque, NM 87185-0747 •a
Office: (505) 284-7850A
Fax: (505) 844-2348

iau, Gary
esday, March 16, 2011 10:32 AM
, Samuel; Undgren, Eric; Gauntt, Randall 0
tito Ph. D. (earl.saitofte.om)'; Bonano, Evansto Jose
Spent Fuel Experiments

Sam, Eric, and Randy,

Earl Saito of GE-Hitachi has contacted me regarding some information on your Spent Fuel experiments, in particular, the BWR experiments. GE, as you can imagine, is trying to gather information on spent fuel pool issues for BWRs.

Can you please send the publically released papers you have written to "prime the pump"? I am sure there is material that you cannot share at this time, but I am looking at our NDA agreements to determine what latitude we may have, if any.

Gary E, Rochau, Manager
Advanced Nuclear Concepts
Nuclear Energy and Global Security Technologies Center
6585/2104, Organization 6771
P.O. Box 5800, MS-1136
Sandia National Laboratories
Albuquerque, New Mexico 87105-1136
Phone: (505)845-7543
Fax: (505)284-4276

 

And, here is a very interesting trip report:

http://pbadupws.nrc.gov/docs/ML1136/ML113610276.pdf

NRC INTERNATIONAL TRIP REPORT
Subject
The Fourth Program Review Group (PRG) and Management Board (MB) Meeting for
Spent Fuel Pool Project in Paris, France.
Dates of Travel, Countries and Organizations Visited
I departed for Paris, France on Saturday November 26, 2011 to attend and participate in
the fourth PRG and MB meeting for the spent fuel Zirc fire project. Meetings were held
at the OECD Issy-les-Moulineaux, France, November 28-29, 2011.
Author, Title, and Agency Affiliation
Ghani Zigh, Senior Level Advisor, DSA:RES.
Sensitivity
Not applicable
Purpose:
To participate in the fourth Program Review Group and Management Board meeting for
the Spent Fuel Pool Project.
Abstract: Summary of Pertinent Points/Issues
In the PRG and MB of the PWR Zirc Fire project:
• PRG meeting was chaired by Techy Zsolt from Hungary.
• MB meeting was chaired by In De Betou Jan from Sweden.
• I made detailed technical presentations and explanations on the program review,
program of work and budget, phase experimental data and analytical
comparison, and the next phase technical design plan.
• Deliverables were discussed.
• Sensitivity of the data was discussed.
• Schedule and budget for 2011 and 2012 were discussed.
• Delay in the financial contribution of University of Pisa (UNIPI) was discussed.
• Technical decision done by PRG through E-mail was discussed.
• Next meeting was proposed to be held in Albuquerque, NM in October of 2012.
Discussion:
In November 28-29, 2011, I participated in the fourth Spent Fuel Pool PRG and MB
meeting held in Paris France. The experiment is taking place in Sandia National
Laboratory (SNL), Albuquerque, NM. In the first day of the meeting, PRG met. In the
meeting, Techy Zsolt from Hungary chaired the meeting as elected in the previous PRG
meeting. As USNRC lead, I gave detailed technical presentations on the program
review as well as the program of work and budget for 2012. Also, I presented the
experimental and analytical results for phase 1 of the program that was concluded
recently as well as the technical design plan for phase 2 of the program that will be
concluded by the end of next year. Additionally, detailed plan as well as deliverables
for 2011 and 2012 for the project was discussed. Finally, the next PRG meeting was
agreed to be held in Albuquerque, NM in October of 2012.
In the second day, the management board meeting was held. The meeting was chaired
by In De Betou Jan from Sweden as elected in the previous MB meeting. In the MB
meeting, I presented a concise report about the status of the program of work for 2011
as well as an overview of the overall program in the PRG meeting. My discussion in the
MB meeting also included the confidentiality of project data and results. Then, the list of
PRG actions from the previous day was approved. Also, the schedule and budget for
2011 and 2012 was discussed.
The MB has taken note of the delay in the financial contribution from UNIPI to the
Project and of its commitment to provide their entire contribution to the Project by the 30
June 2012. Considering this exceptional situation and following provisions from Article 2
c) 4 of the SFP Agreement the MB agreed that UNIPI continue to attend the Project
meetings and receive e-mail exchanged within the Project. However the MB asked the
Operating Agent to hold any further distribution of Project Phase II Data until payment
from UNIPI is received.
MB agreed according to Article 2 c) 3 that any technical decision done by PRG
electronically could be based on two-thirds quorum of the voting strengths.
Notwithstanding the above, the agreement of the USNRC shall be required for
decisions, which might affect the safety of tests, operations and personnel, or
concerning insurance
Pending Actions/Planned Next Steps for NRC
The PRG and MB members for the Spent Fuel Pool Project will meet in Albuquerque,
NM in the October of 2012 to discuss the status of the work and future activities of the
project.
Points for Commission Consideration or Items of Interest
No commission action is required.
Attachments
The draft official summary of the PRG 4 and MB 4 meetings are attached.
“On the Margins”