The Research Of IPWR’s Thermal-Hydraulic Behavior

In cold type Pressurized Water Reactor (IPWR, Inverted Pressurized WaterReactor) was put forward for the first time by Malen in2009in light Water Reactorin waste recycling and utilization of hydride fuel transmutation actinides nuclide plan.IPWR is a new type of hydride (UTh0.5Zr2.25H5.625) for fuel reactor, its fuel elementswaps traditional bar bunch PWR element’s cooling agent for fuel position,fundamentally changes the core of geometrical arrangement. Compared withordinary pressurized water reactor, IPWR has advantage of small core pressure drop,low fuel temperature, more uniform the runner circumferential and small flowvibration phenomenon.（1）、Describing the use of reactor physics calculation procedure MCNP andthermal hydraulic calculation program Fluent; for reference verification of Fluentprogram which applied on IPWR core typical subchannel steady state thermalhydraulic calculation, getting suitable for IPWR core flow and heat transfercalculation of numerical model, it gives a basis for the next calculation.（2）、Through constructing IPWR core cell model, analysising the changes ofinfinite value coefficient with H/HM in different soluble boron concentration. Inensuring certain safety margin, taking a conservative maximum H/HM value, gettinga group of size range which is component cell size according with neutronics limit,and to compare and analysis with the scope of the parameters of the physicalproperties, finally determined that it has a good physical properties of the size range.（3）、Using software Fluent to calculate different grid size of a single fuelelement and coolant channel flow field numerical simulation of IPWR, analysisingand comparing the characteristics of thermal hydraulic in different situations, gettinga group of thermal hydraulic performance which has a better grid size, as the reference and basis for the design of subsequent IPWR core and thermal hydrauliccharacteristics.（4）、Determining IPWR core’s final design parameter, calculating the ratedconditions IPWR core power distribution and power peak factor, getting the corepower of radial and axial distribution, and so gaining the typical subchannel axialheat release situation. Through the establishment of CFD model for the calculation ofIPWR steady state thermal hydraulic, and then analysed the core fuel element in thedistribution of temperature, the flowing heat transfer of coolant characteristics, andcompared with ordinary PWR performance.