Benchmark analysis of SPERT IV reactor
- 作者：Tayyab Mahmood ; mtmalikpk@yahoo.com ; Masood Iqbal ; Ishtiaq Hussain Bokhari
- 关键词：Benchmark ; Neutronic analysis ; SPERT IV ; WIMS ; CITATION
- 刊名：Progress in Nuclear Energy
- 出版年：2012
- 期刊代码：42_01491970
- 类别：pw
- 出版时间：July, 2012
- 卷：58
- 期：Complete
- 页码：6-10
- 文件大小：526 K
摘要
Benchmark calculations have been performed for SPERT IV D-12/25 core. Experimental data of the core was provided by International Atomic Energy Agency (IAEA). Combination of WIMS/D4 and CITATION codes has been used for performing the neutronic analysis of the reactor. Lattice calculations have been performed through WIMS/D4 while 3-dimensional reactor core has been modeled in CITATION. Ten energy groups were considered for these calculations. Energy wise microscopic cross-sections were generated for fuel, control absorber, control follower, guide tube, grid plate, reflector and structural regions separately of the core using WIMS/D4. Thermal neutron flux profiles at different axial and radial locations of the core were evaluated. Critical position of the control rods, excess reactivity, shut down margin, control rod worth, reactivity feed back coefficients and kinetic parameters of the core were estimated. Reasonable agreement has been found between experimentally determined and the calculated parameters.