title: Effective delayed neutron fraction and prompt neutron lifetime of Tehran research reactor mixed-core.
abstract: In this work, kinetic parameters of Tehran research reactor (TRR) mixed cores have been calculated. The mixed core configurations are made by replacement of the low enriched uranium control fuel elements with highly enriched uranium control fuel elements in the reference core. The MTR_PC package, a nuclear reactor analysis tool, is used to perform the analysis. Simulations were carried out to compute effective delayed neutron fraction and prompt neutron lifetime. Calculation of kinetic parameters is necessary for reactivity and power excursion transient analysis. The results of this research show that effective delayed neutron fraction decreases and prompt neutron lifetime increases with the fuels burn-up. Also, by increasing the number of highly enriched uranium control fuel elements in the reference core, the prompt neutron lifetime increases, but effective delayed neutron fraction does not show any considerable change.
authors: Reactors and Accelerators Research and Development School, Nuclear Science and Technology Research Institute (NSTRI), Atomic Energy Organization of Iran (AEOI), Tehran 14399-51113, Iran.
authors: A
authors: A
authors: Lashkari
authors: Reactors and Accelerators Research and Development School, Nuclear Science and Technology Research Institute (NSTRI), Atomic Energy Organization of Iran (AEOI), Tehran 14399-51113, Iran.
authors: H
authors: H
authors: Khalafi
authors: Reactors and Accelerators Research and Development School, Nuclear Science and Technology Research Institute (NSTRI), Atomic Energy Organization of Iran (AEOI), Tehran 14399-51113, Iran.
authors: H
authors: H
authors: Kazeminejad
keywords: Burn-up; Kinetic parameters; Mixed core; Research reactor; Safety analyses