The high-flux reactor PIK with 100 MW power will allow to obtain the thermal neutron flux density in the heavy water reflector tank more than 1015cm-2 • s_1 and a record that has no analogues in the world - 5 • 1015 cm-2 • s_1 in the central experimental beam.
The experimental capabilities of the reactor PIK are determined not only by the high intensity of the thermal neutron beams, which is approximately an order of magnitude higher than the existing medium-power reactors have, but also the planned development of a hot, cold and ultracold neutron sources, that will produce neutron beams with neutrons of other energies with high performances.
At the reactor PIK there are planned to build the cold neutron source for neutron experiments on the horizontal beams HEC-3. The cold neutron source a liquid deuterium will be used as moderator at a temperature of 20-25 K, which is the best moderator for the reactor with heavy water reflector. We expected to get the cold neutron flux density at the reactor face around 6 • 1010- 1.77 • 10 11 cm-2 • s_1 and with heat deposition 6.5-8 kW in CNS in different places of their location in heavy water reflector.
The constructed at reactor PIK in the Petersburg Nuclear Physics Institute named by B.P. Konstantinov of National Research Center «Kurchatov Institute)) the cold neutron source are the world class scientific instruments, and their neutron behaviours allow the reactor PIK be one of the few in the world, which has considerable potential in cold and ultracold neutrons application in various fields of science and technology. The cold and neutron source will significantly expand the instrument experimental base of the reactor PIK.
Distribution of unperturbed neutron fluxes F and heat load Qy in the reactor at 100 MW
Fl - Flux density of fast neutrons E > 5 keV. F2 - Flux density of epithermal neutrons 5 keV > E > 0.6 eV. F3 - Flux density of thermal neutrons E < 0.6 eV.
CNS HEC-3 brightness and Gain
Heat remove principle
CNS design key points Neutron calculation CNS neutron performances (moderator and MC shape optimization, brightness, CN flux density, heat load) Thermal-hydraulic calculation Moderator temperature, heat removal, CNS elements temperature Stress analysis Stresses in CNS in-pile part at working condition Safety analysis report Hydrogen and Nuclear safety