Yurdunaz Çelik

发表

Benchmark study of particle and heavy-ion transport code system using shielding integral benchmark archive and database for accelerator-shielding experiments

Y. Iwamoto, N. Matsuda, S. Kunieda, 2021, Journal of Nuclear Science and Technology.

High-energy nuclear data uncertainties propagated to MYRRHA safety parameters

G. Van den Eynde, H. Iwamoto, A. Stankovskiy, 2018, Annals of Nuclear Energy.

Energy multiplication and fissile fuel breeding limits of accelerator-driven systems with uranium and thorium targets

S. Şahin, B. Şarer, Yurdunaz Çelik, 2015 .

Evaluation of integral quantities in an accelerator driven system using different nuclear models implemented in the MCNPX Monte Carlo transport code

S. Şahin, B. Şarer, Yurdunaz Çelik, 2013 .

ADVANTG hybrid code application for the analysis of neutron field depression in uranium foils activated in the MARK III converter of the BR1 reactor

G. Van den Eynde, E. Malambu, J. Wagemans, 2020 .

Three-dimensional neutronic calculations for a fusion breeder APEX reactor using some libraries

B. Şarer, Yurdunaz Çelik, M. Günay, 2011 .

Neutronic investigations of a laser fusion driven lithium cooled thorium breeder

S. Şahin, B. Şarer, Yurdunaz Çelik, 2014 .

Impact of intermediate and high energy nuclear data on the neutronic safety parameters of MYRRHA accelerator driven system

G. V. D. Eynde, A. Stankovskiy, Yurdunaz Çelik, 2017 .

Neutronic design of MYRRHA reactor hall shielding

G. V. D. Eynde, A. Stankovskiy, Yurdunaz Çelik, 2017 .

Utilization of nuclear waste plutonium and thorium mixed fuel in candu reactors

Sümer Şahin, Başar Şarer, Yurdunaz Çelik, 2016 .

Comparisons of the Calculations Using Different Codes Implemented in MCNPX Monte Carlo Transport Code for Accelerator Driven System Target

S. Şahin, B. Şarer, Yurdunaz Çelik, 2012 .

Radiation source terms of MYRRHA reactor components and equipment

G. V. D. Eynde, J. Engelen, S. Şahin, 2016 .