Thermal Hydraulic Analyses of LEU Target Plates for Mo-99 Production

Conversion from mastered High-Enriched Uranium to Low Enriched Uranium target for Molybdenum production constituted a challenge for nuclear engineering to evaluate its behavior during the three phases (irradiation, cooling and post irradiation). The present work is a contribution to thermal hydraulic analysis of Low Enriched Uranium target plate’s behavior during irradiation using CFD model. Neutronic calculation, target properties and cooling parameters of Korea Atomic Energy Research Institute (KAERI) research group were used as an input in our model. The results obtained with CFD numerical model show that the irradiation conditions are below thermal margins and are approximately close to those obtained by using TMAP code. The developed CFD model will be extended to analyze the thermal hydraulic behavior of Low Enriched Uranium target plates at cooling period (natural convection) and at transfer period (in contact with air).

[1]  K. Mcclellan,et al.  Corrigendum to “Thermophysical properties of U3Si2 to 1773 K” [J. Nucl. Mater. 464 (2015) 275–280] , 2016 .

[2]  H. Nemati,et al.  Numerical study of flow over annular-finned tube heat exchangers by different turbulent Models , 2014 .

[3]  Daeseong Jo,et al.  Neutronic and thermal hydraulic analyses of LEU targets irradiated in a research reactor for Molybdenum-99 production , 2014 .

[4]  Daeseong Jo,et al.  Development of thermal hydraulic and margin analysis code for steady state forced and natural convective cooling of plate type fuel research reactors , 2014 .

[5]  H. Ryu,et al.  DEVELOPMENT OF HIGH-DENSITY U/AL DISPERSION PLATES FOR MO-99 PRODUCTION USING ATOMIZED URANIUM POWDER , 2013 .

[6]  Abou Elmaaty Talal,et al.  Thermal contact resistance and ambient temperature effects on the cooling of Mo99 plate targets inside the hot cell , 2013 .

[7]  Ahmad Jahed Mushtaq,et al.  Management of radioactive waste from molybdenum-99 production using low enriched uranium foil target and modified CINTICHEM process , 2009 .

[8]  Masood Iqbal,et al.  Low enriched uranium foil plate target for the production of fission Molybdenum-99 in Pakistan Research Reactor-1 , 2009 .

[9]  Ho Jin Ryu,et al.  PERFORMANCE EVALUATION OF U-Mo/Al DISPERSION FUEL BY CONSIDERING A FUEL-MATRIX INTERACTION , 2008 .

[10]  I. Bokhari,et al.  Neutronic and thermal hydraulic analysis for production of fission molybdenum-99 at Pakistan Research Reactor-1 , 2008 .

[11]  J. L. Snelgrove,et al.  Development of annular targets for {sup 99}MO production. , 1999 .

[12]  H. Ache,et al.  Production Techniques of Fission Molybdenum-99 , 1987 .

[13]  S. Khan,et al.  Numerical investigation of critical range for the occurrence of secondary peaks in the Nusselt distribution curve , 2018 .

[14]  J. M. Park,et al.  RECENT ACTIVITIES OF KAERI RELATED TO FISSION MO-99 , 2014 .

[15]  G. Solbrekken,et al.  Thermal-Mechanical Analysis of Varying Boundary Conditions on a LEU Foil Based Molybdenum-99 Plate Processing Target , 2010 .

[16]  G. Solbrekken,et al.  ENGINEERING DESIGN OF LEU FOIL BASED TARGET FOR HIGH VOLUME PRODUCTION OF MO-99 , 2008 .

[17]  Dan Wachs,et al.  RERTR Fuel Developmemt and Qualification Plan , 2007 .

[18]  J. Snelgrove,et al.  IRRADIATION TESTS OF Mo ISOTOPE PRODUCTION EMPLOYING URANIUM METAL FOILS* , 1998 .

[19]  Production and Supply of Molybdenum-99 A. Background , 2022 .