Radioactive isotope production in the fast neutron nuclear reactors

Abstract

The present work reviews the primary benefits of radioactive isotope production in the fast neutron reactors the accumulated foreign and local experience in usage of this type of reactors for radioactive isotope production, and also the potential new trends in development of the existing technologies. The main advantage of isotope production in the fast neutron reactors is their high capacity and lower value in general as compared with the accelerating installations. One nuclear reactor may produce dozens of different isotopes including Cj-60, Sr-89 (targets on the base of yttrium), Ni-63 (targets on the base of copper), Eu-152, Eu-154, Sm-145, Sn-117n, Cu-64 and others. It should also be emphasized that a number of radioisotopes are most efficiently produced only in fast and intermediate neutron spectra, which is not possible in nuclear thermal reactors and, above all, in research reactors. Studies have shown that the organization of large-scale production of radioisotopes can significantly increase the economic attractiveness of fast-neutron reactors.

Rapid assessment of integrated nuclear cogeneration projects using multi‐criteria indices

“…Higher cost of thermal desalination than membrane processes; small possibility of carryover of radioactive species into the product water which needs to be avoided by placing intermediate loops; need to use more exotic materials of construction for the process equipment from corrosion considerations 3 Land based nuclear desalination using hybrid schemes [SDG 6,9,11,13] A combination of membrane and thermal desalination plants can be supported by the nuclear power plant to meet its own requirements of both demineralized water for cooling applications as well as service water for other on and off-site purposes. 7,9,11,13] The low grade waste heat discharged into the ambient can be used as input to run low temperature power cycles that use organic liquids as the working fluid, thus enabling additional carbon free electricity production Inherently low thermodynamic efficiencies of low temperature power cycles; higher cost of electricity produced 11 Nuclear waste heat for refrigeration applications [SDG 9,11,13] Nuclear waste heat can be made to act as the essentially cost-free thermal energy source for heat pump devices along with nuclear electricity for applications such as building heating. The heat may also be used to run absorption refrigeration cycles for building/facility cooling applications on the power plant premises…”

“…A few examples of how nuclear power, via cogeneration projects can substitute the use of fossil fuels in meeting some of the most important requirements of mankind 6,9,11,13] Thermal energy (in the form of steam) from a coastal nuclear power plant can be used to evaporate saline water at a maximum temperature of about 120 C, which is then condensed to obtain salt free fresh water (demineralized grade). The process is carried out using staged processes like MSF, MED, MED-TVC, or MED-MVC.…”

“…Nuclear techniques for waste water management and fresh water recovery [SDG 6,11,12,13] Nuclear power plants use water for many applications other than condenser cooling (service water, fire water, spent fuel management, etc.) which generate waste water streams as well.…”

“…12 One of the best known and widely practiced examples of cogeneration is the production of medically and industrially important radionuclides which can only be generated artificially in nuclear facilities via irradiation of certain target materials. [13][14][15][16] Risovanyi 13 considers isotope production in fast reactors, while Dash et al 14 describe the specific case of Lu-177 production starting with different target material for irradiation. General overviews of using power reactors for isotope production are also available in literature.…”

“…Another important opportunity is production of hydrogen through water splitting technologies like low and high‐temperature electrolysis as studied by El‐Emam and Khamis 9 and through thermochemical routes as described by Dincer et al 10,11 Techno‐commercial analysis of the use of advanced reactors for hydrogen production has recently been performed by Khan 12 . One of the best known and widely practiced examples of cogeneration is the production of medically and industrially important radionuclides which can only be generated artificially in nuclear facilities via irradiation of certain target materials 13‐16 . Risovanyi 13 considers isotope production in fast reactors, while Dash et al 14 describe the specific case of Lu‐177 production starting with different target material for irradiation.…”