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| | number = ML20054M297 | | | number = ML20054M297 |
| | issue date = 10/31/1979 | | | issue date = 10/31/1979 |
| | title = Analytical Model for Estimating Drag Forces of Rigid Submerged Structures Caused by LOCA & Safety Relief Valve Ramshead Air Discharges,Suppl for X-Quencher Air Discharges. | | | title = Analytical Model for Estimating Drag Forces of Rigid Submerged Structures Caused by LOCA & Safety Relief Valve Ramshead Air Discharges,Suppl for X-Quencher Air Discharges |
| | author name = Lasher L, Rogers A, Townsend H | | | author name = Lasher L, Rogers A, Townsend H |
| | author affiliation = GENERAL ELECTRIC CO. | | | author affiliation = GENERAL ELECTRIC CO. |
Latest revision as of 02:51, 14 November 2023
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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20117J6531985-04-30030 April 1985 Generic Emergency Response Info Sys (Basic Rtad) Software Validation ML20108F2611985-02-28028 February 1985 Addendum 1 to Power Generation Control Complex Design Criteria & Safety Evaluation ML20093F5321984-06-30030 June 1984 Resolution of Applicable Unresolved Safety Issues & Generic Issues for Gessar II ML20027E5561981-06-30030 June 1981 Suppression Pool Scrubbing Factors for Postulated BWR Accident Conditions, Info Rept ML19290B6801979-11-21021 November 1979 Pages to 22A4365, Interim Containment Loads Rept - Mark III Containment, Nonproprietary Version ML20054M2971979-10-31031 October 1979 Analytical Model for Estimating Drag Forces of Rigid Submerged Structures Caused by LOCA & Safety Relief Valve Ramshead Air Discharges,Suppl for X-Quencher Air Discharges ML20150E0901978-12-0404 December 1978 ADS Solenoid Valve Reliability Demonstration Availability Engr Rept 50. Eval of 1 of 3 Types of Valves to Be Used on Crosby & Dikkers S/Rvs.Info Compiled from 10 Domestic Plants ML20147H3181978-11-30030 November 1978 Recirculation Pump Shaft Seal Leakage Analysis ML20148A3991978-09-29029 September 1978 Evaluation of Acoustic Pressure Loads on BWR/6 Internal Components 1985-04-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20199B0731986-05-31031 May 1986 Safety Evaluation Report Related to the Design Approval of the Gessar II BWR/6 Nuclear Island Design.Docket No. 50-447. (General Electric Company) ML20155G1061986-04-25025 April 1986 Nonproprietary Rev 21 to Amend 21 to Gessar II,238 Nuclear Island ML20132F7131985-07-31031 July 1985 Safety Evaluation Report Related to Final Design Approval of the Gessar II BWR/6 Nuclear Island Design.Docket No. 50-447.(General Electric Company) ML20117J6531985-04-30030 April 1985 Generic Emergency Response Info Sys (Basic Rtad) Software Validation ML20126E0191985-04-0404 April 1985 Response to Gessar Source-Term Issue 9:Suppression Pool Bypass in Bwrs ML20108F2611985-02-28028 February 1985 Addendum 1 to Power Generation Control Complex Design Criteria & Safety Evaluation ML20126D2841985-02-15015 February 1985 Rev 2 to GESSAR-II App 15.D.3,BWR/6 PRA, GESSAR-II App C, Event Trees & GESSAR-II App D,Fault Trees ML20090E1491984-07-12012 July 1984 Gessar II External Event Risk ML20093F5321984-06-30030 June 1984 Resolution of Applicable Unresolved Safety Issues & Generic Issues for Gessar II ML20126D3121983-12-29029 December 1983 Marked-up Pages to GESSAR-II Seismic Event Uncertainty Analysis, Forwarded W/Jf Quick to DG Eisenhut ML20126D3041983-11-17017 November 1983 Marked-up Pages to GESSAR-II Internal Event PRA Uncertainty Analysis Forwarded W/ Jf Quick to DG Eisenhut ML20126J1151983-11-17017 November 1983 Pages 2-7 - 2-16 of GESSAR-II Internal Event PRA Uncertainty Analysis.Portions Deleted ML20126D2871983-11-0707 November 1983 Sanitized Pages 2-17 & 2-18 to GESSAR-II Fire & Flood External Event Analysis Forwarded by Jf Quirk to DG Eisenhut ML20112F9671983-10-24024 October 1983 Speech Entitled, Aerosol Instrumentation for Marviken Aerosol Transport Tests Presented at 830915-16 Conference. Viewgraphs from Ge/Nrc 840320 Meeting Encl ML20126D2991983-09-21021 September 1983 Sanitized Pages to GESSAR-II Seismic Event Analysis Forwarded W/Jf Quirk to DG Eisenhut ML20080C1211983-07-31031 July 1983 Rev 0 to Confirmatory Soil-Structure Interaction Analyses for GESSAR-II ML20077G7321983-07-22022 July 1983 Amend 19 to GESSAR-II ML20077B6961983-07-18018 July 1983 Amend 18 to GESSAR-238 ML20072H5101983-06-15015 June 1983 Nonproprietary Amend 16 to GESSAR-II,providing Assessment of Design Features Which Reduce Sabotage Risk ML20072H5301983-06-15015 June 1983 Amend 17 to GESSAR-II,furnishing New App 1G & Revised Section 1.8 & Clarifying Discrepancies in Text ML20071N5681983-05-24024 May 1983 Amend 15 to GESSAR-II ML20064G4021982-12-21021 December 1982 Nonproprietary Version of Amend 12 to Gessar II ML20066J5171982-11-0808 November 1982 Amend 9 to GESSAR-II ML20065N3391982-09-23023 September 1982 Amend 7 to Gessar II ML20063L5181982-08-31031 August 1982 Amend 6 to Gessar ML20058G5531982-07-30030 July 1982 Amend 5 to Gessar II ML20052G2171982-03-19019 March 1982 Nonproprietary Version of Amend 2 to Application for Final Design Approval Review of 238 Nuclear Island Gessar II Containing Probabilistic Risk Assessment ML20049H2651982-02-12012 February 1982 Chapter 2 to Gessar, Site Characteristics. ML20049H2641982-02-12012 February 1982 Chapter 1 to Gessar, Introduction & General Description of Plant. ML20049H2671982-02-12012 February 1982 App 3A to Gessar, Seismic Soil Structure Interaction Analysis of Nuclear Island. ML20049H2941982-02-12012 February 1982 Chapter 17 to Gessar, Qa. ML20049H2931982-02-12012 February 1982 Chapter 16 to Gessar, Tech Specs. ML20049H2921982-02-12012 February 1982 App 15B to Gessar, BWR/6 Generic Rod Withdrawal Error Analysis. ML20049H2911982-02-12012 February 1982 App 15A to Gessar, Plant Nuclear Safety Operational Analysis. ML20049H2901982-02-12012 February 1982 Chapter 15 to Gessar, Accident Analysis. ML20049H2891982-02-12012 February 1982 Chapter 14 to Gessar, Initial Test Program. ML20049H2881982-02-12012 February 1982 Chapter 13 to Gessar, Conduct of Operations. ML20049H2871982-02-12012 February 1982 Chapter 12 to Gessar, Radiation Protection. ML20049H2861982-02-12012 February 1982 Chapter 11 to Gessar, Radwaste Mgt. ML20049H2851982-02-12012 February 1982 Chapter 10 to Gessar, Steam & Power Conversion Sys. ML20049H2841982-02-12012 February 1982 App 9A to Gessar, Fire Hazard Analysis. ML20049H2831982-02-12012 February 1982 Chapter 9 to Gessar, Auxiliary Sys. ML20049H2821982-02-12012 February 1982 Chapter 8 to Gessar, Electric Power. ML20049H2801982-02-12012 February 1982 App 6A to Gessar, Improved Decay Heat Correlation for LOCA Analysis. ML20049H2791982-02-12012 February 1982 Chapter 6 to Gessar, Esfs. ML20049H2781982-02-12012 February 1982 Chapter 5 to Gessar, RCS & Connected Sys. ML20049H2771982-02-12012 February 1982 App 4A to Gessar, Control Rod Patterns & Associated Power Distribution for Typical Bwr. ML20049H2761982-02-12012 February 1982 Chapter 4 to Gessar, Reactor. ML20049H2751982-02-12012 February 1982 App 3H to Gessar, Effect of Concrete Annulus Below Elevation (-) 5 ft,3 Inches,On Seismic Design Loads & Bldg Responses. ML20049H2741982-02-12012 February 1982 App 3G to Gessar, Pipe Failure Analysis. 1986-05-31
[Table view] |
Text
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Supplement 1 October 1979 .
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ANALYTICAL MODEL FOR ESTIMATING DRAG FORCES ON RIGID SUBMERGED STRUCTURES SUPPLEMENT FOR X-QUENCHER AIR DISCHARGES L E. LASHEH i
GEN ER AL $ ELECTRIC assussa;;
P
NED0-21471-01 78NED99R Supplement 1 Class 1 October 1979 ANALYTICAL MODEL FOR ESTIMATING DRAG FORCES ON RIGID SUBMERGED STRUCTURES CAUSED BY LOCA AND SAFETY RELIEF VALVE RAMSHEAD AIR DISCHARGES SUPPLEMENT FOR X-QUENCHER AIR DISCHARGES L. E. Lasher Reviewed:
H. E. Townsend, Manager Containment Methods Approved:
bh+u3t-r
A. E. Rogers, Manager Containment Tech ology Approved: p n,s / ~ ,u ,
J. Jacobson, Manager Reactor and Containment Design
DISCLAIMER OF RESPONSIBILITY I
Neither the General Electric Company nor any of the contributors to this document makes any warranty or-representation (express or implied) with respect to the accuracy, completeness, or usefulness of the information contained in this document or that the use of such information may not infrinae privately owned. rights; nor do they assume any responsibility for liability or damage of any kind wich m:y result from the use of any of the information contained, in this document.
NED0-21471-01 CONTENTS l t
PAGE ABSTRACT y
- 1. INTRODUCTION 1
- 2. MAJOR ASSUMPTIONS 2
- 3.
SUMMARY
3 0
NED0-21471-01 ILLUSTRATIONS FIGURE TITLE PAGE
- 1. Schematic of the Four-Bubble Model for X-Quencher Air Discharge 4 iv
fled 0-21471-01 ABSTRACT The discharge of air from a quencher will induce an unsteady water motion in'the suppression pool due to air bubble oscillation and create forces on submerged structures. This supplement provides a method for estimation these forces on the basis of an analytical model developed for spherical bubbles.
V l
NED0-21471-01 l
- 1. INTRODUCTION Following a safety relief valve (SRV) discharge from an X-quenche'r, the oscillating air bubbles formed by the discharge result in fluid drag loads on structures submerged in the suppression pool. The total fluid loading is composed of an acceleration-drag component and a standard-drag component.
The methods of estimating the acceleration drag and standard drag developed for the ramshead air discharges in the basic report of this supplement also apply to the air bubbles exiting an X-quencher. It is assumed that four identical air bubbles oscillating in phase are formed between each pair of arms of an X-quencher (see Figure 1).
1
NED0-21471-01 i
- 2. MAJOR ASSUMPT13NS
- 1. Those assumptions concerning oscillating bubbles made in Section 2
-of the basic report are also applicable to this supplement. The same bubble-dynamics equations given for air bubbles from ramshead SRV d.ischarge devices satisfy the essentials for air bubbles from X-quencher discharge devices. j l
- 2. It is assumed that four identical spherical bubbles oscillating in
! phase are formed in an X-quencher, one between each pair of arms. This assumption is supported by the following facts: -
l
- a. The hole pattern in the quencher arm forces the water preceding the steam-air mixture to flow toward the space between the arms.
The steam-air mixture following the water is carried in the same direction. Rapid expansion of the mixture leads to coalescence of the small streams into one big bubble between each pair of arms.
~
- b. Movies taken of discharges from perforated pipes show the formation of one big bubble around a cluster of holes. They clearly indicate the rapid coalescence of the streams into one big bubble.
- c. Observations from film ctudies of scaled X-quencher tests show the formation of four spherical bubbles, one between each pair of arms.
o 2
NED0-21471-01
- 3.
SUMMARY
The calculations carried out for X-quencher air bubbles are identical to those described in Section 3 of the basic report on ramshead air bubble discharges. Equation A80 may be used in the case when the four quencher bubbles from the same SRV line are considered to be synchronously fonned and of equal strength.
h 3
NED0-21471-01 i
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! I SIDE VIEW Figure 1. Schematic of the Four-Bubble Model for X-Quencher Air Discharge 4
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I GEN ER AL h ELECTRIC