Zobrazeno 1 - 10
of 25
pro vyhledávání: '"Erwin Alhassan"'
Autor:
Erwin Alhassan, Dimitri Rochman, Alexander Vasiliev, Mathieu Hursin, Arjan J. Koning, Hakim Ferroukhi
Publikováno v:
Nuclear Science and Techniques. 33
In this work, we explore the use of an iterative Bayesian Monte Carlo (iBMC) method for nuclear data evaluation within a TALYS Evaluated Nuclear Data Library (TENDL) framework. The goal is to probe the model and parameter space of the TALYS code syst
Autor:
Arjan J. Koning, Dimitri Rochman, Stephan Pomp, Petter Helgesson, Erwin Alhassan, Henrik Sjöstrand, M. Österlund
Publikováno v:
Annals of Nuclear Energy. 96:158-169
For several decades reactor design has been supported by computer codes for the investigation of reactor behavior under both steady state and transient conditions. The use of computer codes to simulate reactor behavior enables the investigation of va
Autor:
Arjan J. Koning, Erwin Alhassan, Michael Österlund, Henrik Sjöstrand, Dmitri Rochman, Petter Helgesson, Stephan Pomp
Publikováno v:
Progress in Nuclear Energy. 88:43-52
The current nuclear data uncertainties observed in reactor safety parameters for some nuclides call for safety concerns especially with respect to the design of GEN-IV reactors and must therefore be reduced significantly. In this work, uncertainty re
Autor:
Hakim Ferroukhi, Erwin Alhassan, D. Rochman, Alexander Vasiliev, Arjan J. Koning, Henrik Sjöstrand
Publikováno v:
Annals of Nuclear Energy. 139:107239
In this work, a method is proposed for combining differential and integral benchmark experimental data within a Bayesian framework for nuclear data adjustments and multi-level uncertainty propagation, using the Total Monte Carlo method. First, input
Autor:
Arjan J. Koning, Michael Wohlmuther, R.M. Bergmann, Hakim Ferroukhi, Alexander Vasiliev, Erwin Alhassan, D. Rochman
Publikováno v:
EPJ Web of Conferences, Vol 239, p 13005 (2020)
A lot of research work has been carried out in fine tuning model parameters to reproduce experimental data for neutron induced reactions. This however is not the case for proton induced reactions where large deviations still exist between model calcu
Publikováno v:
EPJ Web of Conferences, Vol 239, p 22003 (2020)
In this work, an overview on the relevance of the nuclear data (ND) uncertainties with respect to the Light Water Reactors (LWR) neutron dosimetry is presented. The paper summarizes results of several studies realized at the LRT laboratory of the Pau
Autor:
Henrik Sjöstrand, Ali Al-Adili, Andreas Solders, Cecilia Gustavsson, Vasily Simutkin, Arjan J. Koning, Dimitri Rochman, Carl Hellesen, Mattias Lantz, Petter Helgesson, Stephan Pomp, Erwin Alhassan, Michael Österlund
Publikováno v:
Nuclear Data Sheets. 123:220-224
We describe the research program of the nuclear reactions research group at Uppsala University concerning experimental and theoretical efforts to quantify and reduce nuclear data uncertainties rele ...
Autor:
Arjan J. Koning, Henrik Sjöstrand, Jesper Rydén, Petter Helgesson, Dimitri Rochman, Stephan Pomp, Erwin Alhassan
Publikováno v:
Progress in Nuclear Energy
The Total Monte Carlo methodology (TMC) for nuclear data (ND) uncertainty propagation has been subject to some critique because the nuclear reaction parameters are sampled from distributions which ...
Publikováno v:
Annals of Nuclear Energy. 73:478-483
In this work, we present results of fuel depletion analyses performed for a potential LEU core of Ghana’s Miniature Neutron Source Reactor (GHARR-1) using the Monte Carlo N-particle extended (MCNPX) neutron transport code. Depletion calculation was
Publikováno v:
Nuclear Science and Engineering. 177:321-336
Precise assessment of propagated nuclear data uncertainties in integral reactor quantities is necessary for the development of new reactors as well as for modified use, e.g., when replacing UO2 fue...