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  3. طراحی حفاظ پرتویی بهینه برای یک راکتور آب سبک تحت فشار کوچک مقیاس
طراحی حفاظ پرتویی بهینه برای یک راکتور آب سبک تحت فشار کوچک مقیاس
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طراحی حفاظ پرتویی بهینه برای یک راکتور آب سبک تحت فشار کوچک مقیاس

دهقان بنادکی، زینب Dehghan Banadaki, Zeynab

Optimal Radiation Shielding Design for a Small-Sized Pressurized Light Water Reactor

Dehghan Banadaki, Zeynab | 2025

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  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 58836 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Hosseini, Abolfazl; Maleki Moghaddam, Nader
  7. Abstract:
  8. One of the main challenges in the development of small-scale reactors is meeting radiation protection requirements. Alongside these requirements, shielding design must be carried out in such a way that, while minimizing weight and volume, it ensures the safety of personnel and sensitive equipment under various operational conditions. Conventional reactor shielding design methods are primarily based on trial-and-error and designer experience. Consequently, the resulting designs are seldom fully optimized, effective, or efficient. In this study, to achieve an optimized shielding design for a small-scale PWR reactor, a multi-objective method based on a genetic algorithm, coupled with the ANISN computational code (for performing particle transport calculations), has been employed. The optimized shielding configuration obtained from the optimization algorithm was simulated using the MCNP code, and the precise dose value after the shield was calculated. Using this method, the thickness and arrangement of the various shield layers were optimized to reduce the total dose (neutron and gamma) after the shield, as well as the total weight and volume of the shield. To evaluate and compare the proposed method with the conventional shielding design approach, a design sample from the SAVANNAH nuclear reactor was examined. In this study, using optimization techniques, the reactor shielding was redesigned, and the results were compared with the original design. In the optimization process related to the SAVANNAH reactor, two scenarios were considered. The first scenario imposed no constraints on the selection of materials for the shield layers; the second scenario involved applying constraints on material selection. The results in the first scenario indicate that the shield weight decreased by 18 to 21 percent, its volume by 10 to 13 percent, and the total dose by 10 to 15 percent. In the second scenario, reductions of 7 to 15 percent in weight, 3 to 16 percent in volume, and 4 to 7 percent in total dose were observed. These values indicate the superiority of the optimized shield over the reference shield design. In the final section, considering two scenarios (non-use of lead and use of lead), the preliminary shield design for the studied reactor was addressed. The results of the first scenario show a 2 to 5.5 percent reduction in shield weight and an 11 to 41 percent reduction in total dose. In the second scenario, a 3 to 10 percent reduction in weight and a 36 to 83 percent reduction in total dose were observed. These results demonstrate that the proposed optimized shielding design performs significantly better than the initially specified values for weight and dose in the reactor under consideration
  9. Keywords:
  10. Genetic Algorithm ; Monte Carlo Method ; Neutron Sourses ; Gamma Source ; ANISN Code ; Radiation Shielding

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