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Prospects of using different clad materials in a material test research reactor – Part 1 – The kinetic parameters
Authors:Farhan Muhammad  Asad Majid
Affiliation:1. Engineering Phys. and Math. Dept., Faculty of Engineering, Cairo Univ., Giza, Egypt;2. National Center of Nuclear Safety and Radiation Control, Atomic Energy Authority, P.O. Box 7551, Nasr City 11762, Cairo, Egypt;1. Nuclear Materials Research Division, Korea Atomic Energy Research Institute, 989-111, Daedeok-daero, Yuseong-gu, Daejeon 34057, Republic of Korea;2. Department of Advanced Materials Science and Engineering, Sungkyunkwan University, 2066, Seobu-ro, Jangan-gu, Suwon 16419, Republic of Korea;1. Department of Aeronautical Engineering, Jawaharlal College of Engineering and Technology, Palakkad, Kerala 679301, India;2. Department of Manufacturing Engineering, School of Mechanical Engineering, Vellore Institute, of Technology Vellore, Tamil Nadu 632014, India;1. Advanced Nuclear Engineering System Department, University of Science and Technology, 217 Gajeong-Ro Yuseong-Gu, Daejeon 305-350, Republic of Korea;2. Korea Atomic Energy Research Institute, 1045 Daeduk-Daero, Dukjin-Dong, Yuseong-Gu, Daejeon 305-353, Republic of Korea
Abstract:The kinetic parameters 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 separately with stainless steel-316 and zircaloy-4. Calculations were carried out to find the core excess reactivity, neutron flux spectrum, prompt neutron generation time and effective delayed-neutron fraction. Nuclear reactor analysis codes including WIMS-D4 and CITATION were employed to carry out these calculations. It was observed that at the beginning of life, the excess reactivity was maximum at 0.054110 Δk/k when zircaloy-4 was used as clad while it was minimum at ?0.365650 Δk/k when stainless steel-316 was the clad as compared to 0.017945 Δk/k for aluminum. The thermal neutron flux at the mid of the central flux trap increased by 59.9% and 12.5% for stainless steel and zircaloy-4 clads, respectively, from the flux of the original aluminum clad. The prompt neutron generation time was maximum at 45.36 μs when stainless steel-316 was the clad while it was minimum at 44.03 μs for the original aluminum clad. The effective delayed-neutron fraction was maximum at 0.007185 for the original aluminum clad while it was minimum at 0.007078 for stainless steel clad.
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