ML20062A608

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Thermal-Hydraulic Design Analysis Rept for BWR High Density Fuel Storage Racks, Presenting Nuclear Energy Svcs Test Results.Local Boiling Will Not Occur in Any Fuel Assembly W/Max Spent Fuel Storage Temp
ML20062A608
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 05/30/1978
From: Guasco G
DAIRYLAND POWER COOPERATIVE
To:
Shared Package
ML20062A597 List:
References
NES-81A0548, NES-81A0548-R01, NES-81A548, NES-81A548-R1, NUDOCS 7810160151
Download: ML20062A608 (31)


Text

NES 81A0548, Rev. 1 7/17/78 l

TIIEliMAL-IIYDRAULIC DESIGN ANALYSIS REPORT FOR THE LACROSSE BOILING WATER REACTOR HIGli DENSITY FUEL STORAGE RACKS Prepared Under NES Project 5101 For The DAIRYLAND POWER COOPERATIVE NUCLEAR ENERGY SERVICES, INC.

Danbury, Connecticut 06810

.,,, _. q Prepared by: G.

Guasco gpM@M4J Approved by:

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Date: :ay 30, 19753 79/o/Go/5/ P

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l TABLE OF CONTENTS i

Page i

1.

SUMMARY

1 2.

INTRODUCTION

~2 i

I 3.

METHOD OF ANALYSIS AND ASSUMPTIONS 3

1 4.

RESULTS OF ANALYSIS AND CONCLUSIONS 4

APPENDIX A - LACBWR EXPANDED FUEL POOL 4

VERIFICATION OF ADEOUATE COOLING a

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1 1.

SUMMARY

The adequacy of natural circulation flow to cool the scent fuel assemblies in the rack matrix was verified by escablishing, for the worst row of assemblies, a thermal'-hydraulic balance between the driving head produced by decay heat generation and the pres-sure losses existing in the natural circulation flow path.

Calculations have shown that under conservative assumptions the maximum assembly exit temperatures are below the saturation tem-perature of the pool water at fuel assembly elevations.

Conse.

quently, local boilina~will not occur in any fuel assembly even with the bulk temperaLore of the spent fuel pool at its maximum value.

i 1

1 2.

INTRODUCTION ~

In the,NES rack design the cross flow of water between adjacent fuel assemblies is prevented by the stainless cells in the fuel rack.

The effect is such that each of the fuel assemblies becomes isolated and, therefore, sits in its own thermal chimney.

The chief thermal-hydraulic concern is the possibility of local boiling due to flow starvation in some cells of the rack matrix as a result of excessive pressure losses in the natural circulation loops established in the spent fuel pool.

The adequacy of the natural circulation flow to cool the hottest assembly in the rack configuration has been verified by esta-blishing a thermal-hydraulic balance for the worst row of assemblies.

Pressure losses in the downcomers, in the rack inlet plenum, and along the fuel assemblies were explicitly considered in the analysis.

Crossflows in the rack inlet plenum area have been conservatively neglected.

The analysis assumes a two-tier design with both upper and lower levels storing spent fuel assemblies.

It is conceivable that at some time only the lower tier will be utilized.

The full two-tier case, however, was determined to be more limiting and is therefore used in the calculations.

The purpose of the analysis is to demonstrate that, even under the most conservative circumstances, local boiling will not occur in the most adversely located fuel assemblies which, as a result of flow maldistribution, might receive less than the fuel pool average assembly flow rate.

I t

l 1

l 2

3.

METHOD OF ANALYSIS AND ASSUMPTIONS The natural circulation flow is calculated by establishing a thermal hydraulic balance for the worst row of assemblies.

The flbw is maintained by the-thermal driving head or draft produced by the decay heat generation in each assembly.

The pool itself is modeled as a large volume with a bulk temperature unaffected by local disturbances.

The pressure losses considered in the analysis include:

1.

Friction losses in the downcomer region, in the rack inlet plenum and in the fuel assembly.

2.

Losses in bends (including the right angle turn that the flow must negotiate to turn from the horizontal rack inlet plenum channel into the vertical fuel assemblies).

1 3.

Form losses in the fuel assemblies at the inlot, outlet and grid spacer locations.

4.

Form losses due to the lower fuel assembly inlet nozzle geometry.

The chief concern is the possibility of substantial pr' essure drop along the inlet manifold channel, causing flow starvation of the fuel assemblies in the limiting fuel assembly string.

The effect of the bundle shroud has effectively been accounted it" by utilizing a corresponding assembly flow area and hy.raulic diameter aloneisnegligiblh.Thefrictionlossduetotheshroudwall Cross-flows have been neglected.

Flow to cells is assumed to be available only from the downcomer.

Coolant from the central cask handling region is conservatively neglected.

All fuel assemblies are assumed to be generating heat at a rate corresponding to 1.4 times the average power fuel assembly.

A pool bulk temperature of 150'F is assumed.

The 2etailed thermal-hydraulic calculations are presented in Appendix A.

i 3

e 4.

RESULTS OF ANALYSIS AND CONCLUSIONS The thermal-hydraulic calculations indicate that even with the mos t co"nservative assumptions, the natural circulation in the spent fuel pool is adequate to preclude local boiling by a substantial margin.

The maximum temperature increase in the assembly with the minimum flow is 23.2*F which would result in an outlet temperature of 173.2*F assuming a bulk pool tempera-ture of 150*F.

The saturation temperature corresponding to the static head at the top of the fuel assembly is 236*F.

l 4

1

APPENDIX A LACBWR EXPANDED FUEL POOL VERIFICATION OF ADEQUATE COOLING r

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