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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20080S6761984-02-29029 February 1984 Draft Site Redress Plan ML20083C8921983-12-27027 December 1983 Final Rept of Crbr Piping & Valve Technical Support Team ML20085A7361983-07-0606 July 1983 Rev 2 to Vol 2 to CRBRP-3, Assessment of Thermal Margin Beyond Design Base (Tmbdb) ML20076D3201983-05-31031 May 1983 Rev 1 to Crbr Project Heat Transport Sys In-Containment Piping Reserve Seismic Margins ML20072B3561983-05-27027 May 1983 Crbr Erosion & Sediment Control Plan Rept ML20084L9931983-03-31031 March 1983 Rev 5 to Hypothetical Core Disruptive Accident Considerations in Crbrp, Vol 2, Assessment of Thermal Margin Beyond Design Base ML20071F1971983-03-10010 March 1983 Adequacy of Crbr Program Reactor Vessel NDE Insps ML20072B6401983-03-0404 March 1983 Crbr Program Heat Transport Sys Incontainment Piping Reserve Seismic Margins ML20079L5131983-02-10010 February 1983 Sodium Slug Energy Absorption Capability of Modified Crbr Closure Head, Westinghouse Crbr Engineering Study Rept ML20064J9381983-01-0707 January 1983 Crbr Reliability Assurance Activities ML20070H8321982-12-31031 December 1982 Assessment of Unprotected Loss of Flow Accident at End of Cycle-4 in Crbr Heterogeneous Core Design ML20070H8521982-12-23023 December 1982 Freezing of Driver Fuel Upon Entry to Inner Blanket ML20070M0801982-12-21021 December 1982 Reactor Vessel Core Support Cone Structural Integrity ML20028E9371982-11-30030 November 1982 Crbr Plant Verification of FORE-2M Computer Code,Part II-Comparison w/EBR-11 Natural Circulation Experiments. ML20028B4811982-11-23023 November 1982 Thermal Margin Beyond Design Basis (Tmbdb) Melting Scenario. ML20070C8921982-10-31031 October 1982 Aerosol Release from Sodium-Concrete Reactions. Prototype Hydrogen Filter Preliminary Test Results Encl ML20070C9171982-10-31031 October 1982 Hydrogen Distribution in Breeder Reactor Containments, Summary Rept.Miscellaneous Updates to CRBRP-3,Vol 2 Info on Containment Cleanup Sys & Revised Response to Question CS760.144 on Axisymmetric Distribution of Temps Encl ML20062H0821982-08-31031 August 1982 Limited Const Activities Rept ML20083M7271982-08-31031 August 1982 Thermal Margin Beyond Design Base (Tmbdb) Sodium-Concrete Penetration Margins Assessment for Crbr Plant ML20062D6121982-08-0404 August 1982 Hypothetical Core Disruptive Accident Considerations in Crbrp:Assessment of Thermal Margin Beyond Design Base, Vol 2,Revision 4 ML20065A3701982-07-16016 July 1982 Draft Revision 1 to Analysis of Nominal Heat Removal Capacity of Crbr in Natural Circulation Mode ML20024E4851982-06-30030 June 1982 Clinch River Breeder Reactor Plant Sys Design Description - Nuclear Island HVAC Sys, Rev D ML20054F1371982-05-31031 May 1982 Verification of Natural Circulation in Crbr Plant - Update ML20054G4881982-05-31031 May 1982 Crbr Special Stress & Criteria Considerations, Crbr Engineering Study Rept ML20054G4801982-05-31031 May 1982 Crbr Special Matls Considerations, Crbr Engineering Study Rept ML20054G4651982-05-31031 May 1982 Crbr Matls Data Base, Crbr Engineering Study Rept ML20053E8661982-05-27027 May 1982 Historical Rept on Crbr Site. ML20053E8721982-05-27027 May 1982 Archeological Investigations in Crbr Project Area 1981-82. ML20054G4561982-04-30030 April 1982 Crbr Transition Joints, Crbr Engineering Study Rept ML20071J5971982-03-31031 March 1982 Hypothetical Core Disruptive Accident Considerations in Crbrp:Energetics & Structural Margin Beyond Design Base, Vol 1,Revision 4 ML20041C8241982-02-28028 February 1982 Summary Rept on Conduct of Crbr Key Sys Reviews. ML20065Q3991981-09-30030 September 1981 Energy Economic Data Base (Eedb) Program, Phase 4 Final Rept & Fourth Update ML20065Q3571981-08-26026 August 1981 Greater Commitment Needed to Solve Continuing Problems at TMI, Rept to Congress ML19341C2521981-02-28028 February 1981 Clinch River Breeder Reactor Project Circulation Verification Program Pretest Predictions for Fftf Natural Circulation Tests Initiated at 100% & 75% Power/Flow Conditions. ML20065Q3631981-01-31031 January 1981 Inel as Site for Large Lmfbr ML19345B7831980-11-28028 November 1980 Prediction of Fftf Natural Circulation Test Results Using Clinch River Breeder Reactor Plant Project Methodology. ML20065Q3741980-10-31031 October 1980 Alldos - Computer Program for Calculation of Radiation Doses from Airborne & Waterborne Releases ML20065U2971980-07-31031 July 1980 ORIGEN2 - Revised & Updated Version of Oak Ridge Isotope Generation & Depletion Code ML19305C6261980-03-31031 March 1980 Hypothetical Core Disruptive Accident Considerations,Vol 2: Assessment of Thermal Margin Beyond Design Base. ML19345B7881980-03-31031 March 1980 Demo Pretest Predictions for Fftf Transient Natural Circulation Tests. Demo Pretest Predictions of Reactor Inlet Flows & Temps During Fftf Transient Natural Circualtion Test, Encl ML19296A2151979-02-0909 February 1979 to Hypothetical Core Disruptive Accident Considerations in Crbrp, Vol 1, Energetics & Structural Margin Beyond Design Base. ML20040E0301977-11-30030 November 1977 Rept on Development of Criteria for Designation of Health Manpower Shortage Areas. ML20065U3271975-10-31031 October 1975 Improved Matl Accounting for Pu Processing Facilities & U-235 HTGR Fuel Fabrication Facility ML20065Q3681975-01-31031 January 1975 Airdos - Computer Code for Estimating Population & Individual Doses Resulting from Atmospheric Releases of Radionuclides from Nuclear Facilities ML20083C8891974-08-31031 August 1974 Selection of Coolant Boundary Matls for Crbr ML20040D7051971-09-30030 September 1971 Available Industrial Areas,Oak Ridge,Tn. 1984-02-29
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20080S6761984-02-29029 February 1984 Draft Site Redress Plan ML20083C8921983-12-27027 December 1983 Final Rept of Crbr Piping & Valve Technical Support Team ML20083M1611983-10-24024 October 1983 Part 21 Rept Re Noncompliance to ASME Code Test Requirement Involving Nuclear Part Not Receiving Pressure Test Prior to Acceptance.Change Control Procedure Revised to Be More Explicit on Types of Documents Utilized ML20085A7361983-07-0606 July 1983 Rev 2 to Vol 2 to CRBRP-3, Assessment of Thermal Margin Beyond Design Base (Tmbdb) ML20023D4071983-05-31031 May 1983 Amend 77 to PSAR ML20076D3201983-05-31031 May 1983 Rev 1 to Crbr Project Heat Transport Sys In-Containment Piping Reserve Seismic Margins ML20072B3561983-05-27027 May 1983 Crbr Erosion & Sediment Control Plan Rept ML20084L9931983-03-31031 March 1983 Rev 5 to Hypothetical Core Disruptive Accident Considerations in Crbrp, Vol 2, Assessment of Thermal Margin Beyond Design Base ML20071F1971983-03-10010 March 1983 Adequacy of Crbr Program Reactor Vessel NDE Insps ML20072B6401983-03-0404 March 1983 Crbr Program Heat Transport Sys Incontainment Piping Reserve Seismic Margins ML20079N3691983-03-0202 March 1983 Amend 76 to PSAR ML20028G4251983-02-28028 February 1983 Amend 75 to PSAR ML20070W2001983-02-28028 February 1983 Corrected Pages to Page Replacement Guide of Amend 75 to PSAR ML20079L5131983-02-10010 February 1983 Sodium Slug Energy Absorption Capability of Modified Crbr Closure Head, Westinghouse Crbr Engineering Study Rept ML20028C2911983-01-31031 January 1983 Crbr PSAR Chapter 17.0-QA,App D Description of NSSS QA Program, Submitted for Inclusion in Amend 75 to PSAR ML20064J9381983-01-0707 January 1983 Crbr Reliability Assurance Activities ML20070H8321982-12-31031 December 1982 Assessment of Unprotected Loss of Flow Accident at End of Cycle-4 in Crbr Heterogeneous Core Design ML20070K6661982-12-31031 December 1982 Amend 74 to PSAR ML20070H8521982-12-23023 December 1982 Freezing of Driver Fuel Upon Entry to Inner Blanket ML20070M0801982-12-21021 December 1982 Reactor Vessel Core Support Cone Structural Integrity ML20057B5651982-12-0909 December 1982 Partially Withheld Commission Paper Re NRDC Vs NRC 82-1962 Re Facility ML20057B5631982-12-0707 December 1982 Partially Withheld Commission Paper Informing Commission of DC Circuit Court Decision Re Facility ML20028E9371982-11-30030 November 1982 Crbr Plant Verification of FORE-2M Computer Code,Part II-Comparison w/EBR-11 Natural Circulation Experiments. ML20028B4681982-11-30030 November 1982 Amend 73 to PSAR ML20028B4811982-11-23023 November 1982 Thermal Margin Beyond Design Basis (Tmbdb) Melting Scenario. ML20065S2491982-10-31031 October 1982 Amend 72 to PSAR ML20070C8921982-10-31031 October 1982 Aerosol Release from Sodium-Concrete Reactions. Prototype Hydrogen Filter Preliminary Test Results Encl ML20070C9171982-10-31031 October 1982 Hydrogen Distribution in Breeder Reactor Containments, Summary Rept.Miscellaneous Updates to CRBRP-3,Vol 2 Info on Containment Cleanup Sys & Revised Response to Question CS760.144 on Axisymmetric Distribution of Temps Encl ML20028A6141982-09-30030 September 1982 Supplementary Manual for F0RE-2M Computer Program. ML20027B9471982-09-30030 September 1982 Amend 71 to PSAR ML20083M7271982-08-31031 August 1982 Thermal Margin Beyond Design Base (Tmbdb) Sodium-Concrete Penetration Margins Assessment for Crbr Plant ML20062H0821982-08-31031 August 1982 Limited Const Activities Rept ML20062N5901982-08-31031 August 1982 Amend 70 to PSAR ML20055C1621982-08-13013 August 1982 Recommends Modifying Proposed Decision Granting in Part Exemption from 10CFR50.12 by Adding Provision Re Endangered Species Act ML20057B5371982-08-10010 August 1982 Partially Withheld Commission Paper to Provide Draft Order Concluding Commission Proceeding on DOE Request for Exemption Per 10CFR50.12 ML20062D6121982-08-0404 August 1982 Hypothetical Core Disruptive Accident Considerations in Crbrp:Assessment of Thermal Margin Beyond Design Base, Vol 2,Revision 4 ML20071K4221982-07-31031 July 1982 Amend 69 to PSAR ML20058J0261982-07-30030 July 1982 Page Replacement Guide for Amend 69 to PSAR ML20058E4561982-07-22022 July 1982 Crbr Plant Rept ML20065A3701982-07-16016 July 1982 Draft Revision 1 to Analysis of Nominal Heat Removal Capacity of Crbr in Natural Circulation Mode ML20054H8261982-06-30030 June 1982 SITE-SUITABILITY Report in the Matter of the Clinch River Breeder Reactor Plant.Docket No. 50-537 ML20024E4851982-06-30030 June 1982 Clinch River Breeder Reactor Plant Sys Design Description - Nuclear Island HVAC Sys, Rev D ML20063D4631982-06-30030 June 1982 Site Preparation Activities Rept ML20063G8551982-06-30030 June 1982 Updated Pages for Ref 106 of PSAR Section 1.6,CRBRP-3,Vol 2, Hypothetical Core Disruptive Accident Considerations in Crbr:Assessment of Thermal Margin Beyond Design Base ML20054K9341982-06-30030 June 1982 Speech Entitled Simulation of Lmfbr ML20071E1011982-05-31031 May 1982 LMFBR Program, Fes ML20054G4881982-05-31031 May 1982 Crbr Special Stress & Criteria Considerations, Crbr Engineering Study Rept ML20054G4801982-05-31031 May 1982 Crbr Special Matls Considerations, Crbr Engineering Study Rept ML20054G4651982-05-31031 May 1982 Crbr Matls Data Base, Crbr Engineering Study Rept ML20054F1371982-05-31031 May 1982 Verification of Natural Circulation in Crbr Plant - Update 1984-02-29
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FREEZING OF DRIVER FUEL UPON ENTRY TO INNER BLANKET
_ Michael Epstein Fauske & Associates, Inc.
" 8212270254 821223 l PDR ADDCK 05000537 .
A .PDR
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FREEZING OF DRIVER FUEL UPON ENTRY TO INNER BLANKET ASSEMBLIES -
We consider a turbulent flow or jet of driver fuel at its freezing temperature flowing " radially" into an inner blanket assembly through a longitudinal failure (or slit) along its steel-hexcan boundary. Freezing of the molten driver fuel will take place on the surfaces of the relatively cold blanket rods as well as on the inner walls of the intact portion of the hexcan. It is of interest to determine whether the molten driver fuel can fill all the interstitial space within the ccmpact blanket-rod structure before solidification is complete between the blanket rods that occupy the .
outer row of the bundle matrix (" blanket inlet region"). The penetration and freezing of the molten driver fuel in the interstices of the bundle will
" weld" the blanket rods together and strengthe'n the blanket assembly against subsequent mechanical or thermal attack by driver fuel.
In keeping with our objective, we focus attention on a representative subchannel within the rod bundle and assume that it can be regarded as a simple parallel-plate channel of gap width 6 equal to the diameter of the wire wrap (minimum spacing between rods = 0.084 cm). An expression for the dis-tance X a solidifying liquid initially at its fusion temperature can pene~-
trate into a cold channel before the channel freezes shut in the inlet region is [1]
[AP+D l = 0.085 i ["}7/11 X
I (1) h (A ag l
( pv 2 j ,
where v and p are the liquid kinematic viscosity and density, respectively, a, is the thermal diffusivity of the solid phase that grows along the channel 1
1
~
wall, A is the solid phase growth constant [1], D = 26 is the hydraulic h
diameter of the freeze channel and AP is the driving pressure for liquid flow.
2 2 3 Taking v = 0.005 .cm /s, o, = 0.0064 cm /s, = 8.6 g/cm for the molten
, (driver) fuel properties; A = 0.5 for fuel crust growth on a solid (blanket) fuel wall; and a driving pressure AP = 0.5 atm corresponding to gravity-driver fuel flow, we get X = 20.4 cm P
Owing to the circuitous path the driver fuel must follow through the rod bundle matrix, the above-predicted penetration distance is egoivalent to a
" straight-line distance" of about 12.0 cm. This distance is somewhat greater than the width of the rod bundle (= 10 cm) and, therefore, the molten driver fuel should fill most of the space between blanket rods with frozen material.
Of course, if the driver fuel is initially superheated, it will readily penetrate the interstitial space between blanket rods, stagnate and then solidify in place.
Reference
- 1. M. Epstein, L. J. Stachyra, and G. A. Lambert, " Transient Solidification in Flow into a Rod Bundle," J. Heat Transfer, Vol. 102, No. 2, pp.
330-334, 1980. '
i Enclosure 6 This enclosure contains the response to item 9 of enclosure 1.
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