RELAP5 Model of the First Wall/Blanket Primary Heat Transfer System

Popov, Emilian L¹  Yoder Jr, Graydon L¹  Kim, Seokho H¹ 

[1]ORNL

关键词: ITER TOKAMAK;    FIRST WALL;    BREEDING BLANKETS;    ALGORITHMS;    R CODES;    COOLANTS;    HEAT TRANSFER;    COMPUTERIZED SIMULATION;    TEMPERATURE CONTROL;    THERMAL EXPANSION;    THERMAL HYDRAULICS;   

DOI  :  10.2172/985287
RP-ID  :  ORNL/TM-2010/57
PID  :  OSTI ID: 985287
Others  :  Other: AT5512020
Others  :  ERATITM
Others  :  US ITER 12101-TD0001-R00
Others  :  TRN: US1006099

学科分类：原子、分子光学和等离子物理

美国|英语

来源: SciTech Connect

【 摘 要 】

ITER inductive power operation is modeled and simulated using a system level computer code to evaluate the behavior of the Primary Heat Transfer System (PHTS) and predict parameter operational ranges. The control algorithm strategy and derivation are summarized in this report as well. A major feature of ITER is pulsed operation. The plasma does not burn continuously, but the power is pulsed with large periods of zero power between pulses. This feature requires active temperature control to maintain a constant blanket inlet temperature and requires accommodation of coolant thermal expansion during the pulse. In view of the transient nature of the power (plasma) operation state a transient system thermal-hydraulics code was selected: RELAP5. The code has a well-documented history for nuclear reactor transient analyses, it has been benchmarked against numerous experiments, and a large user database of commonly accepted modeling practices exists. The process of heat deposition and transfer in the blanket modules is multi-dimensional and cannot be accurately captured by a one-dimensional code such as RELAP5. To resolve this, a separate CFD calculation of blanket thermal power evolution was performed using the 3-D SC/Tetra thermofluid code. A 1D-3D co-simulation more realistically models FW/blanket internal time-dependent thermal inertia while eliminating uncertainties in the time constant assumed in a 1-D system code. Blanket water outlet temperature and heat release histories for any given ITER pulse operation scenario are calculated. These results provide the basis for developing time dependent power forcing functions which are used as input in the RELAP5 calculations.