The MCB Code for Numerical Modeling of Fourth Generation Nuclear Reactors

Oettingen, Mikołaj; Cetnar, Jerzy; Mirowski, Tomasz

doi:10.7494/csci.2015.16.4.329

Cited by 14 publications

(4 citation statements)

References 9 publications

(8 reference statements)

Supporting

Mentioning

Contrasting

Order By: Relevance

“…After all, the solution of the burnup problem performed using the TTA approach delivers the nuclide compositions at the end of the computational period in the same way as the matrix exponential method. The TTA method has been initially implemented in MCB [13,20] over twenty years ago, while recently, with a significantly growing interest in developing new codes, several realisations include TTA, including Serpent [28] and the most recent ones, with modified algorithms based on recursive formulas: DEPTH [29], OMCB [30], IMPC [31] and MODEC [32].…”

Section: Summary and Discussionmentioning

confidence: 99%

“…In this work, one of the latest version of the MCB5 code implemented on supercomputers of the Academic Computer Centre CYFRONET AGH was used for the computation time presentations. The practical issues related to the implementation and automation of the MCB code using Message Passing Interface at high performance computers are available in an associated paper [20]. In the implementation, the benchmarking and validation process were carried out.…”

Section: Methods and Numerical Tool Developments And Comparisonsmentioning

confidence: 99%

See 1 more Smart Citation

Linear Chain Method for Numerical Modelling of Burnup Systems

2021

View full text Add to dashboard Cite

The theoretical aspects of the linear chain method for the numerical modelling of nuclear transmutation systems, and particularly regarding the transmutation trajectory analysis (TTA), are presented. The theoretical background of the TTA method, as an advanced version of the linear chain method, with the detailed description of the applied mathematical set-up and graphical visualisation of transformation chains, is shown. As the TTA method was initially developed at the AGH University of Science and Technology almost 25 years ago, several numerical implementations were introduced worldwide, yet the mathematical improvements or alternative forms of solutions and numerical algorithms were reported since then. The method was also implemented and tested by different research groups, also in confrontation with alternative approaches to the nuclear transformation problem known as the matrix method. The aim of the paper is to present the background of the developed method and its advantages, clarify misunderstandings in the method perception and suggest unexplored options in numerical algorithm implementation.

show abstract

Section: Summary and Discussionmentioning

confidence: 99%

Section: Methods and Numerical Tool Developments And Comparisonsmentioning

confidence: 99%

Linear Chain Method for Numerical Modelling of Burnup Systems

2021

View full text Add to dashboard Cite

show abstract

“…Subsequently, the calculations using the NFCSS system for given sample enrichment and discharge burnup were performed. Where the data about cooling time after the discharge of the sample from the reactor core were available, pure decay calculations were performed using the MCB code [23]. The numerically obtained actinide concentrations in mg/U units were used to calculate the (C/E) ratios for further processing.…”

Section: Validation Proceduresmentioning

confidence: 99%

The Application of Radiochemical Measurements of PWR Spent Fuel for the Validation of Burnup Codes

Oettingen

2022

Energies

View full text Add to dashboard Cite

The paper shows the usage of destructive assay data from PWR fuel samples for the validation of the NFCSS burnup system developed by the IAEA. The results of radiochemical measurements of spent fuel isotopic composition were compared with the results of numerical modelling. In total, 254 samples from 15 PWRs, incorporated in the SFCOMPO database, were applied in the validation study. The paper shows the trends observed in the calculated-to-experimental ratios for eight major actinides and six minor actinides present in spent nuclear fuel. The data were quantified and analysed considering the enrichment, burnup and origin. The obtained results were compared with other studies on burnup validation using different numerical tools. In general, the results of numerical modelling for major actinides show rather good consistency with radiochemical measurements, while the results for minor actinides are less accurate.

show abstract

“…kernel radius, packing fraction, enrichment etc. The numerical model of the reactor was developed using the Monte Carlo continuous energy burnup code (MCB) [6,7]. In the next section, the volumetric homogenization method is comprehensively described.…”

Section: Introductionmentioning

confidence: 99%

Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel

Oettingen

Cetnar

2021

Nukleonika

View full text Add to dashboard Cite

The volumetric homogenization method for the simplified modelling of modular high-temperature gas-cooled reactor core with thorium-uranium fuel is presented in the paper. The method significantly reduces the complexity of the 3D numerical model. Hence, the computation time associated with the time-consuming Monte Carlo modelling of neutron transport is considerably reduced. Example results comprise the time evolutions of the effective neutron multiplication factor and fissionable isotopes (233U, 235U, 239Pu, 241Pu) for a few configurations of the initial reactor core.

show abstract

The MCB Code for Numerical Modeling of Fourth Generation Nuclear Reactors

Cited by 14 publications

References 9 publications

Linear Chain Method for Numerical Modelling of Burnup Systems

Linear Chain Method for Numerical Modelling of Burnup Systems

The Application of Radiochemical Measurements of PWR Spent Fuel for the Validation of Burnup Codes

Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel

Contact Info

Product

Resources

About