Delayed neutron fraction beff

This paper presents a nuclear data sensitivity and uncertainty analysis of the effective delayed neutron fraction beff for critical and subcritical cores of the MYRRHA reactor using the continuous-energy Monte Carlo N-Particle transport code MCNP.

7p christabelhuynh 29-05-2020 13 0   Download

The measured a is successively used to determine the experimental value of the effective delayed neutron fraction as well. According to the experimental results, beff of the HWZPR reactor under study is equal to 7.84e3. This value is finally used to validate the calculation of the effective delayed neutron fraction by the Monte Carlo methods that are discussed in the document.

6p minhxaminhyeu5 30-06-2019 11 0   Download

The present study aims to assess the excess induced reactivity in a Miniature Neutron Source Reactor (MNSR) for a Beyond Design Basis Accident (BDBA) scenario. The BDBA scenario as defined in the Safety Analysis Report (SAR) of the reactor involves sticking of the control rod and filling of the inner and outer irradiation sites with water. At the end of the MNSR core life, 10.

6p minhxaminhyeu3 25-06-2019 15 0   Download