One of the main issues in using materials for nuclear facilities is to minimize the production of the most hazardous radionuclides. In the ideal case, all nuclear reactor materials, except a fuel, should be low-activation. The term “low-activation material” means that this one loses its induced activity in a short time after removal from irradiation. Proposals for building a fusion reactor using low-activation materials are given in Ref.1, 2. For this purpose, low-activation structural materials based on V-Ti-Cr alloys are in the stage of R&D in several countries [3,4]. Another technique to avoid the hazardous activity is in using isotopically enriched materials [5–7]. Although isotopical tailoring option requires tremendous technical efforts and it is too expensive, its application can be first of all assumed for those structural and functional materials which generate very hazardous radionuclides under irradiation. In modern projects of next generation NPPs the preference is given to fast reactors (FRs) with a lead coolant [8]. As it known, the coolant circulating through a FR core is activated, and in the future we should have problems with handling a completed coolant after FR decommissioning or at realization of repair or emergency activities. There, it is desirable to have a low-activation coolant with the low contents of hazardous radionuclides. In papers [9,10] presented at the previous ICONE conferences it was proposed to use lead isotope, Pb-206, as a coolant instead of lead natural, Pb-nat. This paper is devoted to more detailed calculations of accumulating stable bismuth, Bi-209, and polonium radioisotopes, Po-209 (T1/2 = 102 y) and Po-210 (T1/2 = 138 d), in 1 kg of Pb-nat or Pb-206 placed in the core of the BOR-60 type FR.
Skip Nav Destination
10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3596-0
PROCEEDINGS PAPER
Polonium Issue in Fast Reactor Lead Coolants and One of the Ways of Its Solution
G. L. Khorasanov,
G. L. Khorasanov
State Scientific Center of Russian Federation, Obninsk, Kaluga, Russia
Search for other works by this author on:
A. P. Ivanov,
A. P. Ivanov
State Scientific Center of Russian Federation, Obninsk, Kaluga, Russia
Search for other works by this author on:
A. I. Blokhin
A. I. Blokhin
State Scientific Center of Russian Federation, Obninsk, Kaluga, Russia
Search for other works by this author on:
G. L. Khorasanov
State Scientific Center of Russian Federation, Obninsk, Kaluga, Russia
A. P. Ivanov
State Scientific Center of Russian Federation, Obninsk, Kaluga, Russia
A. I. Blokhin
State Scientific Center of Russian Federation, Obninsk, Kaluga, Russia
Paper No:
ICONE10-22330, pp. 711-717; 7 pages
Published Online:
March 4, 2009
Citation
Khorasanov, GL, Ivanov, AP, & Blokhin, AI. "Polonium Issue in Fast Reactor Lead Coolants and One of the Ways of Its Solution." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 2. Arlington, Virginia, USA. April 14–18, 2002. pp. 711-717. ASME. https://doi.org/10.1115/ICONE10-22330
Download citation file:
13
Views
Related Proceedings Papers
Related Articles
Development of Risk Informed Aging Management Program in Decommissioning
ASME J of Nuclear Rad Sci (January,2025)
Fracture Toughness J IC Prediction From Super-Small Specimens (0.2CT, 0.5MM Thick) of a Martensitic Stainless Steel HT-9
J. Eng. Mater. Technol (January,1991)
Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location
ASME J of Nuclear Rad Sci (October,2018)
Related Chapters
A Study of Irradiation-Induced Growth of Modified and Advanced Zr-Nb System Alloys after Irradiation in the VVER-1000 Reactor Core at Temelin NPP
Zirconium in the Nuclear Industry: 20th International Symposium
The Nuclear and Related Industry
Decommissioning Handbook
Environmental and Related Requirements
Decommissioning Handbook