Title :
Neutron dosimetry and 3D neutron transport calculations in the HFR Petten — a powerful tool in detailed neutron monitoring and damage analysis
Author :
Mutnuru, R.K. ; Ketema, D.J. ; van der Marck, S.C.
Author_Institution :
Nucl. Res. & Consultancy Group (NRG), Petten, Netherlands
Abstract :
Dosimetry at the High Flux Reactor in Petten, the Netherlands, serves a variety of purposes ranging from demonstrating compliance with the license for operating the reactor to validating the predictions of DPA in material irradiations. It is also used in the validation of the 3D neutron transport calculations during post-irradiation analysis to normalize the spectrum obtained from these calculations. In this paper, a thorough examination of irradiated steel specimens is carried out using the measurements performed with the neutron activation technique as well as the 3D neutron transport calculations to check the consistency in the resulting DPA values.
Keywords :
dosimetry; fission reactor safety; fission reactor theory; neutron transport theory; 3D neutron transport calculation; MCNP code; damage analysis; high flux reactor; irradiated steel specimen; neutron activation technique; neutron dosimetry; neutron monitoring; post-irradiation analysis; Assembly; Chemical elements; Dosimetry; Fuels; Inductors; Isotopes; Monitoring; Neutrons; Physics; Steel; Activation foils; DPA; MCNP; Neutron Dosimetry; material damage;
Conference_Titel :
Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2009 First International Conference on
Conference_Location :
Marseille
Print_ISBN :
978-1-4244-5207-1
Electronic_ISBN :
978-1-4244-5208-8
DOI :
10.1109/ANIMMA.2009.5503726