title: A new safety channel based on ¹⁷N detection in research reactors.
abstract: Tehran research reactor (TRR) is a representative of pool type research reactors using light water, as coolant and moderator. This reactor is chosen as a prototype to demonstrate and prove the feasibility of (17)N detection as a new redundant channel for reactor power measurement. In TRR, similar to other pool type reactors, neutron detectors are immersed in the pool around the core as the main power measuring devices. In the present article, a different approach, using out of water neutron detector, is employed to measure reactor power. This new method is based on (17)O (n,p) (17)N reaction taking place inside the core and subsequent measurement of delayed neutrons emitted due to (17)N disintegration. Count and measurement of neutrons around outlet water pipe provides a reliable redundant safety channel to measure reactor power. Results compared with other established channels indicate a good agreement and shows a linear interdependency with true thermal power. Safety of reactor operation is improved with installation & use of this new power measuring channel. The new approach may equally serve well as a redundant channel in all other types of reactors having coolant comprised of oxygen in its molecular constituents. Contrary to existing channels, this one is totally out of water and thus is an advantage over current instrumentations. It is proposed to employ the same idea on other reactors (nuclear power plants too) to improve safety criteria.
authors.affiliation: Reactor Research School, Nuclear Science and Technology Research Institute (NSTRI), P.O. Box 143995-1113, Tehran, Iran.
authors.forename: Somayye
authors.initials: S
authors.lastname: Seyfi
authors.affiliation: Department of Energy and Physics, Amirkabir University of Technology, P.O. Box 15875-4413, Tehran, Iran. Electronic address: mgharib2@yahoo.com.
authors.forename: Morteza
authors.initials: M
authors.lastname: Gharib
keywords: BF(3) detector; Delayed neutron from (17)N; Reactor power measurement