Solidification of the strip solution containing cesium-137 using gubka porous inorganic material

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Аннотация

In the Khlopin Radium Institute, during development of extractive partitioning of the liquid high level radioactive waste (HLW), a strip solution containing up to 6.0 × 1011 Bq/dm3 (16.3 Ci/dm3) of 137Cs in the form of a nitric acid solution was collected and temporary stored. To solidify this solution, a batch process using «Gubka» porous inorganic material (PIM) was developed and performed. Since that time, about 18 dm3 of HLW was solidified into 12 sets of «Gubka», reducing the liquid HLW volume by a factor of about 50. «Gubka» sets were placed into special containers, which were sent to the site of the RosRAO Branch in Sosnovy Bor after sealing by welding.

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Авторлар туралы

A. Aloy

Khlopin Radium Institute

Хат алмасуға жауапты Автор.
Email: aloy@khlopin.ru
Ресей, St. Petersburg

A. Vizniy

Khlopin Radium Institute

Email: aloy@khlopin.ru
Ресей, St. Petersburg

T. Koltsova

Khlopin Radium Institute

Email: aloy@khlopin.ru
Ресей, St. Petersburg

D. Shishkin

Khlopin Radium Institute

Email: aloy@khlopin.ru
Ресей, St. Petersburg

Әдебиет тізімі

  1. Nardova A.K., Tumanova O.S. // Proc. Int. Topic Meeting on Nuclear and Hazardous Waste Management. Seattle, 18–23.08.1996. Am. Nucl. Soc. 1996. Vol. 2. P. 2154–2160.
  2. Simmons J.H., Macedo P.B., Barkatt A., Litovitz T.A. // Nature. 1979. Vol. 278. P. 729–731.
  3. Захаров M.A., Потемкина Т.И., Козарь A.A. // Неорган. материалы. 1993. Т. 29. № 3. C. 379–380.
  4. Аншиц Н.Н., Верещагина Т.А., Баюков О.А. Саланов А.Н., Аншиц А.Г. // Физика и химия стекла. 2005. Т. 31. № 3. С. 410–422.
  5. Knecht D.A., Tranter T.J., Aloy A.S., Anshits A.G., Tretyakov A.A., Macheret J. // WM’01: Proc. Waste Management Symp. 2001. P. 79–83.
  6. Aloy A.S., Sapozhnikova N.V., Kol’tsova T.I., Strelnikov A.V. // Proc. 10th Int. Conf. on Environmental Remediation and Radioactive Waste Management (ICEM’05). Glasgow, 4–8.09.2005. Am. Soc. of Mechanical Engineers. 2005. P. 1252–1255.
  7. TRS 377: Minimization of Radioactive Waste from Nuclear Power Plants and Back End of the Nuclear Fuel Cycle. Vienna: IAEA, 1995. P. 59–61.
  8. Есимантовский В.М., Визный А.Н., Галкин Б.Я., Родионов С.А., Шишкин Д.Н. // Четвертая Рос. конф. по радиохимии. Озерск, 20–25.10.2003. ПО “Маяк”, 2003. С. 99–100.
  9. Aloy А.S., Anshits A.G., Tretyakov A.A., Knecht D.A., Tranter T.J., Macheret Y. // Scientific Basis for Nuclear Waste Management XXIII. Boston, 29.11–02.12.1999. Vol. 608. P. 637–642.
  10. Feick G., Hainer R.M. // J. Am. Chem. Soc. 1954. Vol. 76. P. 5860–5863.
  11. Алой А.С., Баранов С.В., Логунов М.В., Слюнчев О.М., Харлова А.Г., Царицына Л.Г. Источники гамма-излучения с цезием-137 (свойства, производство, применение). Озерск: ПО «Маяк», 2013. 232 с.

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2. Fig. 1. External appearance of the “Sponge” blocks (a) and the distribution of salt in the internal pore space of the “Sponge” (b).

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3. Fig. 2. Scheme of curing of 137Cs re-extract using “Sponge” blocks.

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4. Fig. 3. The “PORA” setup for testing the process with a model cesium reextract solution. 1 – electric furnace; 2 – two PNM blocks; 3 – rotary furnace bottom with two PNM blocks; 4 – container with Cs reextract; 5 – case for two PNM blocks saturated with CsNO3; 6 – gas purification system (set of three bubbler-condensers).

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