A5066465529- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Graphite, nuclear technology, radiation studies
- Radiation Therapy and Dosimetry
- Radiation Detection and Scintillator Technologies
- Nuclear and radioactivity studies
- Fusion materials and technologies
- High Temperature Alloys and Creep
- Radiation Effects and Dosimetry
- Radiation Effects in Electronics
- High-Temperature Coating Behaviors
Belgian Nuclear Research Centre
2016-2023
Gazi University
2011-2016
Gazi Hastanesi
2011
To validate the accuracy of general-purpose Monte Carlo Particle and Heavy-Ion Transport code System (PHITS), a benchmark study recent version (version 3.24) PHITS has been conducted using neutron-shielding experiments listed in Shielding Integral Benchmark Archive Database (SINBAD). Five neutron sources were selected, which are generated from (1) 43- 68-MeV proton-induced reaction on thin lithium target, (2) 52-MeV thick graphite (3) 590-MeV lead (4) 500-MeV tungsten (5) 800-MeV tantalum...
Spent nuclear fuel out of conventional light water reactors contains significant amount even plutonium isotopes, so called reactor grade plutonium. Excellent neutron economy Canada deuterium uranium (CANDU) can further burn plutonium, which has been used as a booster fissile material in form mixed ThO2/PuO2 CANDU bundle order to assure criticality. The paper investigates incineration waste and the prospects exploitation rich world thorium reserves reactors. In present work, criticality...
The lack of double-differential cross-section (DDX) data for neutron production below the incident proton energy 200 MeV hinders validation spallation models in technical applications, such as research and development accelerator-driven systems (ADSs). present study aims to obtain experimental DDX ADS target materials this region identify issues related by comparing them with analytical predictions. DDXs (p,xn) reactions natPb 209Bi 100-MeV were measured over an angular range 30° 150° using...
The MCNPX code offers options based on physics packages; the Bertini, ISABEL, INCL4 intra-nuclear models, and Dresner, ABLA evaporation-fission models CEM2k cascade-exciton model. study analyzes main quantities determining ADS performance, such as neutron yield, leakage spectra, proton spectrain target andin beam window calculated by MCNPX-2.5.0 Monte Carlo transport code, which is a combination of LAHET MCNP codes. results obtained simulating different cited above implemented in are...
The Working Party on International Nuclear Data Evaluation Co-operation Subgroup 47 (WPECSG47) entitled "Use of Shielding Integral Benchmark Archive and Database for Validation" was organised from 2019 2022 with the objectives to promote more systematic wider use shielding benchmark experiments in nuclear data (ND) transport code validation development, provide feedback (SINBAD), its further development coordination Expert Group Physics Reactor Systems (EGPRS). Altogether 9 meetings, large...
The effects of both proton and neutron nuclear data libraries on the field produced in light targets transported through shielding material were assessed. general-purpose JENDL-4.0/HE, TENDL-2017, ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, JEFF-3.1.2, JEFF-3.3 benchmarked using MCNP6.2 Monte Carlo transport code. Three experiments from SINBAD database, namely, 52-MeV protons hitting a carbon target 43- 68-MeV 7Li target, selected for benchmarking. This selection was made according to their...
Perturbation of external neutron source can cause significant local power changes transformed into undesired safety-related events in an accelerator driven system. Therefore for the accurate design MYRRHA sub-critical core it is important to evaluate uncertainty responses caused by uncertainties nuclear reaction models describing particle transport from primary proton energy down evaluated data table range. The calculations with a set resulted quite low on perturbation yield interactions...
A measurement campaign in support of nuclear disarmament verification was carried out 2019 on the premises Belgian Nuclear Research Centre, SCK CEN. Well-characterized MOX sources with different types shielding materials were used during campaign. The relative content Pu up to 14%wt and isotopic abundance 239 93%wt. One technologies that deployed neutron coincidence counting 3 He based slab counters. obtained background dead time corrected total reals rates determine mass assayed sample by...
The lateral shielding of a 600 MeV proton linear accelerator beam line in the MYRRHA reactor hall has been assessed using neutronic calculations by MCNPX code complemented with analytical predictions. Continuous losses were considered to define required thickness that meets requirements for dose rate limits. Required thicknesses investigated from viewpoint accidental full loss as well on collimator. results confirm are highly sensitive spatial shape and strongly divergent losses. Therefore...
In the framework of Phase I MYRRHA project implementation, superconducting linear accelerator with proton beam parameters 100 MeV, 4 mA is going to be built. To stop beam, a dump based on Al-6061 alloy designed. The evaluation radiological impact an accidental radioactivity release requires reliable estimates primary radiation source terms associated uncertainties. article addresses propagation nuclear data uncertainties through activation calculations. Total Monte Carlo approach was used...