Cost optimization of ADS design: Comparative study of externally driven heterogeneous and homogeneous two-zone subcritical reactor systems

Gulik, Volodymyr; Tkaczyk, Alan H.

doi:10.1016/j.nucengdes.2014.01.007

Cited by 22 publications

(12 citation statements)

References 21 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…Gen er ally speak ing, the prop erty of the subcritical sys tem to am plify neu tron flux of the ex ternal source is used in most cases in the steady-state subcritical sys tems [12,13]. There fore, it would be of great in ter est to in ves ti gate and an a lyze the prob lem of am pli fy ing prop er ties of the subcritical sys tem in the case of pulsed neu tron sources.…”

Section: Some As Pects Of Prop a Ga Tion Of Neu Tron Pulse Through Thmentioning

confidence: 99%

The pulsed subcritical amplifier of neutron flux driven by high-intensity neutron generator

Бабенко

Pavlovych

Gulik³

2019

NUCL TECH RAD PROT

Self Cite

View full text Add to dashboard Cite

The subcritical re ac tor driven by ex ter nal neu tron source could ap ply as use ful in stru ment for mod ern nu clear en ergy ap pli ca tions re quir ing high-level ir ra di a tion of dif fer ent ma te ri als by the high-en ergy and high-in tense neu tron flux (e. g., nu clear waste trans mu ta tion, radiopharmaceutical pro duc tion, etc.). The prop a ga tion of neu tron pulses through the subcritical nu clear sys tem was con sid ered in the pres ent pa per. Sim ple ho mo ge neous subcritical sys tems and a model of two-zone subcritical re ac tor were computationally in ves tigated us ing Monte Carlo MCNP4c trans port code. The prop a ga tion of one ini tial neu tron pulse and se ries of one hun dred neu tron pulses through the pre sented subcritical nu clear mod els were sim u lated. In this study, the neu tron mul ti pli ca tion fac tor, the neu tron flux, the en ergy am pli fi ca tion fac tor, the to tal en ergy of neu trons in ini tial pulse, etc. were ob tained and an a lyzed. The pre sented cal cu la tions have shown that the con sid ered pulse subcritical sys tems can be suc cess fully used as ef fec tive am pli fi ers of neu tron flux from the ini tial source. The mod el ing re sults in di cate that there is an achieve ment of a sta ble, high level of neu tron flux caused by the ac cu mu la tion of de layed neu trons from pre vi ous pulses in se ries of one hun dred pulses for both ho mo ge neous and het er o ge neous sys tems. Key words: ac cel er a tor-driven sys tem, Monte Carlo cal cu la tion, pulsed re search re ac tor, D-T neu tron gen er a tor IN TRO DUC TION-SOME GEN ERAL CON CEPTS OF USES OF THE SUBCRITICAL MUL TI PLY ING SYS TEMS

show abstract

Section: Some As Pects Of Prop a Ga Tion Of Neu Tron Pulse Through Thmentioning

confidence: 99%

The pulsed subcritical amplifier of neutron flux driven by high-intensity neutron generator

Бабенко

Pavlovych

Gulik³

2019

NUCL TECH RAD PROT

Self Cite

View full text Add to dashboard Cite

show abstract

“…Ця модель дає змогу моделювати проходження нейтронів джерела через різну кількість бетонних шарів різної товщини. В нашому випадку використане плоске джерело швидких нейтронів з енергією 14 МеВ [30], які рухались горизонтально в бік детектора через досліджуваний матеріал. Моделювання нейтронів з енергією саме 14 МеВ корисне для розуміння захисних властивостей матеріалів (D,T)-нейтронних генераторів, установок плазмового фокусу, термоядерних реакторів та ядерних реакторів на швидких нейтронах.…”

Section: теорія та методи моделюванняunclassified

Investigations of Neutron Radiation Shielding Properties for a New Composite Material Based on Heavy Concrete and Basalt Fiber

Romanenko

Holiuk

Nosovsky

et al. 2018

Nucl. and Rad. Safe.

View full text Add to dashboard Cite

The paper presents a new composite material for radiation shielding properties. This material is based on super-heavy concrete reinforced with basalt fiber, which could be used in biological protection systems for neutron radiation sources. The simulation of the neutron transport in the presented material was performed using the Monte Carlo Serpent code. Two types of heavy concretes were considered in the present paper: 1) with ordinary rubble coarse aggregate and 2) with barite coarse aggregate. For each type of concrete, the basalt fiber with dosage from 1 kg/m3 to 50 kg/m3 was added. The current transmission rates were obtained as a result of the neutron-physical modelling for neutron transport from source to detector through the proposed concrete samples with different thicknesses. The obtained modelling results were analyzed from the viewpoint of effectiveness of the radiation shielding properties. Also, elastic and capture microscopic cross-sections were considered for some isotopes and as a result, some aspects of the radiation shielding properties were clarified. The concrete with ordinary rubble coarse aggregate has better radiation shielding properties in case of low concrete thicknesses due to better neutron scattering on light nucleuses. In contrast to this, the concrete with barite coarse aggregate has better radiation shielding properties in case of high concrete thicknesses due to better neutron absorption. It is shown that the addition of basalt fiber to concrete not only improves its mechanical properties and reduces the number and size of microcracks, but also increases the ability to protect against neutron flux. The proposed composite material could be recommended for use with the following neutron sources: (D, T) neutron generators, plasma focus devices, fusion reactors and fast reactors. This research was carried out with the financial support of the IAEA, within the terms and conditions of the Research Contract 20638 in the framework of the Coordinated Research Project (CRP) “Accelerator Driven Systems (ADS) Applications and use of Low-Enriched Uranium in ADS (T33002)” within the project ‘The Two-Zone Subcritical Systems with Fast and Thermal Neutron Spectra for Transmutation of Minor Actinides and Long-Lived Fission Products’.

show abstract

“…The presented model allows the calculation of the passage of neutrons through concrete layers with different thicknesses. The plane source of 14 MeV fast neutrons is used in our model (Kolomiec, 1985;Gulik and Tkaczyk, 2014). All neutrons are moving horizontally from plane source to concrete.…”

Section: Theory and Calculation For Neutron Attenuationmentioning

confidence: 99%

Radiation shielding properties of a novel cement–basalt mixture for nuclear energy applications

Ipbüker

Nulk

Gulik

et al. 2015

Nuclear Engineering and Design

Self Cite

View full text Add to dashboard Cite

Cost optimization of ADS design: Comparative study of externally driven heterogeneous and homogeneous two-zone subcritical reactor systems

Cited by 22 publications

References 21 publications

The pulsed subcritical amplifier of neutron flux driven by high-intensity neutron generator

The pulsed subcritical amplifier of neutron flux driven by high-intensity neutron generator

Investigations of Neutron Radiation Shielding Properties for a New Composite Material Based on Heavy Concrete and Basalt Fiber

Radiation shielding properties of a novel cement–basalt mixture for nuclear energy applications

Contact Info

Product

Resources

About