TAILIEUCHUNG - Nuclear Power System Simulations and Operation Part 4

Tham khảo tài liệu 'nuclear power system simulations and operation part 4', kỹ thuật - công nghệ, cơ khí - chế tạo máy phục vụ nhu cầu học tập, nghiên cứu và làm việc hiệu quả | 34 Nuclear Power - System Simulations and Operation Future woks will simulate the IPR-R1 employing other method to flux calculate. The information about neutron flux predicted by MNCP5 and MCNPX can improve NAA where the sample activity can be estimated knowing neutron flux. Furthermore these codes can characterize the neutron flux in other parts of the reactor where experimental measuring is difficult to be obtained. Position RSR Previous Studies Present Study Experimental Value Model 1 MCNP 4B Model 2 MCNP5 Model 3 MCNPX Value Error Value Error Value Error 1 3 7 10 24 25 29 34 35 38 40 Table A2. Thermal neutron flux x 1011 n cm-2s-1 ANNEX B. Example of RELAP5 code application to IPR-R1 research reactor BI. Introduction The RELAP5 system code was developed to simulate transient scenarios in power reactors such as PWR and BWR but recent works have been performed to investigate the applicability of the code to research reactors operating conditions with good results. Specifically the TRIGA reactors are constructed in a variety of configurations and capabilities with steady-state power levels ranging from 20 kilowatts to 16 megawatts offering true inherent safety . TRIGA is a pool-type reactor that can be installed without a containment building being designed for use by scientific institutions and universities for purposes such as graduate education private commercial research non-destructive testing and isotope production. In the present work the IPR-R1 TRIGA reactor Mark-I model installed in Brazil in operation since 1960 has been modeled for RELAP5 code with the aim of to

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