Prospects of using different clad materials in a material test research reactor – Part 2 – The reactivity feedback coefficients |
| |
| Authors: | Farhan Muhammad Asad Majid |
| |
| Affiliation: | 1. Pakistan Institute of Engineering and Applied Sciences, Islamabad 45650, Pakistan;2. Research in Modeling and Simulation (RIMS) Group, Department of Physics, CIIT, Park Road, Islamabad, Pakistan;1. LPSC, Université Grenoble-Alpes, CNRS/IN2P3, 53, rue des Martyrs, 38026 Grenoble, France;2. Reactor Physics and Systems Behaviour Laboratory (LRS), Nuclear Energy and Safety Department (NES), Paul Scherrer Institut (PSI), 5232 Villigen, Switzerland;3. VTT Technical Research Centre of Finland, Tietotie 3, Espoo FI-02044 VTT, Finland;4. Nuclear Systems Design and Analysis Division, Idaho National Laboratory, 2525 Fremont Ave., P.O. Box 1625, Idaho Falls, ID 83415-3860, USA;1. Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology, Institute of Nuclear and Physical Engineering, Ilkovi?ova 3, 812 19 Bratislava, Slovakia;2. Slovenské elektrárne, MO34 office No. K3/214, 935 35 Mochovce, Slovakia;1. Karlsruhe Institute of Technology, Institute for Neutron Physics and Reactor Technology, Herman-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany;2. The Pennsylvania State University, Department of Mechanical and Nuclear Engineering, 206 Reber Building, University Park, PA 16802, USA;1. Nuclear Science and Technology Development Center, National Tsing Hua University, 101, Sec. 2, Kuangfu Rd., Hsinchu 30013, Taiwan, ROC;2. Department of Engineering and System Science and Institute of Nuclear Engineering and Science, National Tsing Hua University, 101, Sec. 2, Kuangfu Rd., Hsinchu 30013, Taiwan, ROC |
| |
| Abstract: | The reactivity feedback coefficients of a material test research reactor using stainless steel-316 and zircaloy-4 as clad were calculated. For this purpose, the aluminum clad of an MTR was replaced with stainless steel-316 and zircaloy-4. Calculations were carried out to find the fuel temperature reactivity feedback coefficient, clad temperature reactivity feedback coefficient, moderator temperature reactivity feedback coefficient and moderator density reactivity feedback coefficient. Nuclear reactor analysis codes including WIMS-D4 and CITATION were employed to carry out these calculations. It is observed that the average values of fuel temperature reactivity feedback coefficient, moderator temperature reactivity coefficient and moderator density reactivity coefficient from 38 °C to 50 °C, at the beginning of life, were maximum in magnitude for stainless steel-316 cladded fuel, followed by aluminum and least for the zircaloy-4 cladded fuel. The fuel temperature feedback coefficient increased in magnitude by 47.37% for stainless steel-316 and decreased by 4.72% for zircaloy-4 clad. The moderator temperature feedback coefficient increased in magnitude by 60.41% for stainless steel-316 and decreased by 3.03% for zircaloy-4 clad, while the moderator density feedback coefficient showed an increase in magnitude of 59.18% for stainless steel-316 and a decrease of 7.63% for zircaloy-4 clad. Zircaloy-4 gave a positive value for clad temperature feedback coefficient, while the others two did not have any clad temperature feedback coefficient. |
| |
| Keywords: | |
| 本文献已被 ScienceDirect 等数据库收录！ |
|
