System for monitoring of energy release in the core of a boiling-water reactor

Assessment of the correlation method for determining the parameters of two-phase coolant in a vk-50 core

“…Such sensors make it possible to determine the dependence of the propagation velocity of a neutron flux perturbation over the height of the core from the local flow structure of the steam-water mixture. The results of height measurements with in-core monitoring of the energy release in VK-50 are presented in the present article [3].…”

“…Such sensors make it possible to determine the dependence of the propagation velocity of a neutron flux perturbation over the height of the core from the local flow structure of the steam-water mixture. The results of height measurements with in-core monitoring of the energy release in VK-50 are presented in the present article [3].Review of Foreign Studies. The cross-correlation function of the currents of sensors distributed over height was first used to determine the parameters of the steam-water flow in the core of boiling-water vessel reactors at the beginning of the 1970s, when publications appeared concerning measurements performed on the Lingen (West Germany) [4], Garigliano (Italy) [5], Fukushima-1 (Japan) [6], and other reactors.…”