مجله فناوری و انرژی هسته ای

امکان‌سنجی تولید رادیوایزوتوپهای مختلف با استفاده از تابش دهی هدف نمک مذاب اورانیوم توسط شتابدهنده پروتونی سیکلوترون MeV 30

https://doi.org/10.48308/nucte.2022.99018
دوره 1، شماره 1 - شماره پیاپی 1
بهار 1401
صفحه 36-48
مجله فناوری و انرژی هسته ای

نویسندگان

زهره غلامزاده
فرخ خوش احوال

سازمان انرژی اتمی

چکیده
استفاده از نمک­های مذاب فلوراید اورانیوم-توریم در ترکیبات مختلف به طور گسترده­ای در راکتورهای نمک مذاب انجام شده است. در واقع یکی از مهمترین مزیت این نمک­های مذاب، دمای ذوب و جوش بسیار بالای آنها است. لذا استفاده از هدف­های نمک مذاب فلوراید اورانیوم می­تواند نیاز به انتقال حرارت را در سیستم­های تولید رادیوایزوتوپ توسط شتابدهنده برطرف سازد. لذا در این کار، بررسی اولیه استفاده از این نمک مذاب به عنوان ماده هدف در شتابدهنده سیکلوترون به منظور تولید رادیوایزوتوپها مختلف انجام گردید. از کد محاسباتی MCNPX و ALICE/ASH جهت محاسبات استفاده شد. نتایج حاصل از این کار نشان می­دهد. استفاده از این نمک های مذاب می تواند معضلات انتقال حرارت هدف و محدودیت اعمال جریان باریکه پروتونی بر ماده هدف را برطرف سازد. ضمن اینکه تولید و برداشت محصولات مختلف رادیوایزوتوپ را به طور همزمان فراهم می سازد. با بهینه کردن هندسه هدف می توان بهره تولید محصولات مختلف شکافت را در ماده نمک مذاب افزایش داد. همچنین استفاده از شتابدهنده می­تواند وابستگی تولید رادیوایزوتوپهای مورد استفاده پزشکی و صنعت را به راکتورهای هسته­ای کاهش دهد.

کلیدواژه‌ها

کد MCNPX
کد ALICE/ASH
رادیوایزوتوپ
تابش دهی پروتونی
هدف نمک مذاب اورانیوم-فلوراید

عنوان مقاله English

Feasibility study of 99Mo radioisotope production using uranium molten salt target irradiation by 30 Mev proton Cyclotron

نویسندگان English

زهره غلامزاده
فرخ خوش احوال
AEOI
چکیده English

Fluoride Uranium-Thorium molten salts are widely used in the molten salt reactors in different compositions. The most important characteristic of the MSRs is high melting and boiling point. Therefore, the use of molten salt solution of uranium fluoride can eliminate the need for heat transfer in radioisotope production systems by accelerators. The initial study of the use of this molten salt as a target material in a cyclotron accelerator was carried out to generate various radioisotopes. We used MCNPX and ALICE/ASH. The results of this study show that the use of these molten salts can solve the problem of heat transfer and limit the application of proton beam flow on the target material. While also producing and harvesting various radioisotope products simultaneously.By optimizing the target geometry, we can increase the production rate of the different fission products in molten salt material. In addition, the use of accelerators can reduce the dependence of the production of radioisotopes used in medicine and industry to nuclear reactors.

کلیدواژه‌ها English

  • Two-phase flow
  • Gamma-ray attenuation
  • flow rate
  • Artificial Neural Networks
  • NaI(Tl)
  • Detector counts
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  3. Williams, D.F., Toth, L.M. and Clarno, K.T., 2006. Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR) (pp. 1-69). United States. Department of Energy.
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  5. Konobeyev, A.Y., Korovin, Y.A., Lunev, V.P. and Blann, M., 2006. ALICE/ASH-Pre-compound and evaporation model code system for calculation of excitation functions, energy and angular distributions of emitted particles in nuclear reactions at intermediate energies.
  6. Mirvakili, S.M., Alizadeh, M., Vaziri, A.J., Gholamzadeh, Z. and Davari, A., 2015. Computational investigation of 99Mo production yield via proton irradiation of natU and 232Th targets. Applied Radiation and Isotopes, 101, pp.127-134.
  7. Malambu, E., 2004. Sub-critical core design of the small-scale XADS: sizing, drawings, fuel handling. Deliverable D12–revision 1 of PDS-XADS project. FIKW-CT-2001-00179, September.
  8. Ottewitte, E.H., 1992. Cursory First Look at the Molten Chloride Fast Reactor as an Alternative to the Conventional BATR Concept.
  9. Ignatiev, V., Merzlyakov, A., Afonichkin, V., Khokhlov, V. and Salyulev, A., 2002, October. Transport properties of molten-salt reactor fuel mixtures: the case of Na, Li, Be/F and Li, Be, Th/F salts. In Seventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, 14th-16th October, Jeju, Republic of Korea.
  10. Williams, D.F., Toth, L.M. and Clarno, K.T., 2006. Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR) (pp. 1-69). United States. Department of Energy.
  11. Pelowitz, D. B. 2008. MCNPX User's Manual. Vol. LA-CP-07-1473 Version 2.6.0. Los Alamos, NM: U. S. Department of Energy, Los Alamos National Laboratory.
  12. Konobeyev, A.Y., Korovin, Y.A., Lunev, V.P. and Blann, M., 2006. ALICE/ASH-Pre-compound and evaporation model code system for calculation of excitation functions, energy and angular distributions of emitted particles in nuclear reactions at intermediate energies.
  13. Mirvakili, S.M., Alizadeh, M., Vaziri, A.J., Gholamzadeh, Z. and Davari, A., 2015. Computational investigation of 99Mo production yield via proton irradiation of natU and 232Th targets. Applied Radiation and Isotopes, 101, pp.127-134.
  14. Malambu, E., 2004. Sub-critical core design of the small-scale XADS: sizing, drawings, fuel handling. Deliverable D12–revision 1 of PDS-XADS project. FIKW-CT-2001-00179, September.
  15. Ottewitte, E.H., 1992. Cursory First Look at the Molten Chloride Fast Reactor as an Alternative to the Conventional BATR Concept.
  16. Ignatiev, V., Merzlyakov, A., Afonichkin, V., Khokhlov, V. and Salyulev, A., 2002, October. Transport properties of molten-salt reactor fuel mixtures: the case of Na, Li, Be/F and Li, Be, Th/F salts. In Seventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, 14th-16th October, Jeju, Republic of Korea.
  17. Williams, D.F., Toth, L.M. and Clarno, K.T., 2006. Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR) (pp. 1-69). United States. Department of Energy.
  18. Pelowitz, D. B. 2008. MCNPX User's Manual. Vol. LA-CP-07-1473 Version 2.6.0. Los Alamos, NM: U. S. Department of Energy, Los Alamos National Laboratory.
  19. Konobeyev, A.Y., Korovin, Y.A., Lunev, V.P. and Blann, M., 2006. ALICE/ASH-Pre-compound and evaporation model code system for calculation of excitation functions, energy and angular distributions of emitted particles in nuclear reactions at intermediate energies.
  20. Mirvakili, S.M., Alizadeh, M., Vaziri, A.J., Gholamzadeh, Z. and Davari, A., 2015. Computational investigation of 99Mo production yield via proton irradiation of natU and 232Th targets. Applied Radiation and Isotopes, 101, pp.127-134.
  21. Malambu, E., 2004. Sub-critical core design of the small-scale XADS: sizing, drawings, fuel handling. Deliverable D12–revision 1 of PDS-XADS project. FIKW-CT-2001-00179, September.
  22. Ottewitte, E.H., 1992. Cursory First Look at the Molten Chloride Fast Reactor as an Alternative to the Conventional BATR Concept.
  23. Ignatiev, V., Merzlyakov, A., Afonichkin, V., Khokhlov, V. and Salyulev, A., 2002, October. Transport properties of molten-salt reactor fuel mixtures: the case of Na, Li, Be/F and Li, Be, Th/F salts. In Seventh Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, 14th-16th October, Jeju, Republic of Korea.
  24. Williams, D.F., Toth, L.M. and Clarno, K.T., 2006. Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR) (pp. 1-69). United States. Department of Energy.
  25. Pelowitz, D. B. 2008. MCNPX User's Manual. Vol. LA-CP-07-1473 Version 2.6.0. Los Alamos, NM: U. S. Department of Energy, Los Alamos National Laboratory.
  26. Konobeyev, A.Y., Korovin, Y.A., Lunev, V.P. and Blann, M., 2006. ALICE/ASH-Pre-compound and evaporation model code system for calculation of excitation functions, energy and angular distributions of emitted particles in nuclear reactions at intermediate energies.
  27. Mirvakili, S.M., Alizadeh, M., Vaziri, A.J., Gholamzadeh, Z. and Davari, A., 2015. Computational investigation of 99Mo production yield via proton irradiation of natU and 232Th targets. Applied Radiation and Isotopes, 101, pp.127-134.
  28. Malambu, E., 2004. Sub-critical core design of the small-scale XADS: sizing, drawings, fuel handling. Deliverable D12–revision 1 of PDS-XADS project. FIKW-CT-2001-00179, September.

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