Neutronic modeling of a subcritical system with corium particles and water from international benchmark

Smirnov, A D; Bogdanova, E. V.; Pugachev, P. A.; Saldikov, Ivan; Ternovykh, Mikhail; Тихомиров, Г. В.; Takezawa, Hiroki; Muramoto, Takeshi; Nishiyama, Jun; Obara, Toru

doi:10.26583/npe.2020.2.12

Cited by 4 publications

(1 citation statement)

References 8 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…This article continues a series of papers in which detailed benchmark description and results of preliminary explicit effective multiplication factor calculations were presented [7,8], and also developed programming tool for visualizing the calculation results was introduced [9]. Current paper focuses on more accurate calculation results of several parameters such as neutron fluxes, reaction rates, and relative FOM (Figure of Merit) as well as improved effective multiplication factor calculation results (results improvement was achieved by correcting calculation model in MCU).…”

Section: Introductionmentioning

confidence: 96%

Monte Carlo codes benchmarking on sub-critical fuel debris particles system for neutronic analysis

Smirnov

Bogdanova

Pugachev

et al. 2021

Journal of Nuclear Science and Technology

View full text Add to dashboard Cite

Fuel debris removal is the most challenging part of damaged nuclear power station decommissioning. It is important to carry out nuclear safety calculations accurately and quickly enough. Here, it was clarified that modern codes based on the Monte Carlo method were capable of performing neutronic analysis with the same accuracy and without significant differences in the results. The benchmark calculations were performed using three codes: MVP, Serpent, and MCU. In this study, the comparison focused on multiplication factor, neutron fluxes and reaction rates relative difference, and calculation time of many fuel debris particles system. Then the calculation results were used when codes comparing. It was shown that the calculation results showed good agreement between all codes. It was assumed that minor differences in the thermal range of neutron fluxes can be caused by different thermal neutrons scattering treatment for all codes. The study also showed that solving such problems requires significant computing power and time. It has been proven that the statistical geometry model in the MVP and the explicit stochastic geometry model in the Serpent have the possibility to provide solutions with the same accuracy, but much faster.

show abstract

Section: Introductionmentioning

confidence: 96%

Monte Carlo codes benchmarking on sub-critical fuel debris particles system for neutronic analysis

Smirnov

Bogdanova

Pugachev

et al. 2021

Journal of Nuclear Science and Technology

View full text Add to dashboard Cite

show abstract

Neutron-physical characteristics modeling of light water reactors critical corium slurry in water

Ternovykh

Abdumalikov

Ryzhov

2020

J. Phys.: Conf. Ser.

View full text Add to dashboard Cite

In this paper, the idea of modifying the benchmark by increasing effective multiplication factor value in the considered system without increasing the number of particles under consideration and fuel enrichment is discussed. The technology of data transmission, processing and comparison of the results of neutron-physical calculations using three modern codes developed in different countries and implementing the Monte Carlo method has been worked out. For the corium and water mixture parameters search, the method conventionally called the gradient descent method is used. The search method for areas of critical state corium slurry in water is described. This method can be used to justify nuclear safety in the corium extraction and transportation processes. The methodology is based on the combined use of 1-D and 3-D criticality calculations capabilities of the SCALE 6.2 program pack. Fall of corium particles in water simulation benchmark version is formulated. The possibility of using the algorithm to find the parameters of a corium and water mixture is demonstrated. This benchmark includes the critical state of corium slurry in water and assumes the use of regular structures in the formation of geometric models. The proposed version of the critical benchmark for the corium particles in water state contains 55% fuel.

show abstract

CORIUMSITY program code for the consequences analysis of a severe core melt accident

Saldikov

Bogdanova

Pugachev

et al. 2020

J. Phys.: Conf. Ser.

View full text Add to dashboard Cite

As part of the tasks to improve the nuclear safety of nuclear power plants, a new program code was developed. The CORIUMSITY program code developed, considered in this work, is intended to analyze the scenario in which an accident at a nuclear power plant is simulated with the melting of the core and the formation of the so-called “corium” - a mixture of nuclear and structural materials of the nuclear reactor core, formed as a result of thermal and mechanical impact during an accident. The CORIUMSITY program code, is intended to analyze several scenarios of different accidents, include an accident with reactor core melting. The functions of this code can help in solving many urgent nuclear safety problems. One of the main methods of operation of the CORIUMSITY code algorithms is the matrix exponential method, which consists in using a matrix function of a square matrix, in which as values are used indicators corresponding to nuclides from the CORIUMSITY code database. The program implements an iterative Euler method for solving the system of levels of nuclear fuel burnup. The CORIUMSITY code was verified with benchmark data to assess the accuracy of the calculation.

show abstract

Neutronic modeling of a subcritical system with corium particles and water from international benchmark

Abstract: И з в е с т и я в у з о в • Я д е р н а я э н е р г е т и к а • № 2 • 2 0 2 0 135

Cited by 4 publications

References 8 publications

Monte Carlo codes benchmarking on sub-critical fuel debris particles system for neutronic analysis

Monte Carlo codes benchmarking on sub-critical fuel debris particles system for neutronic analysis

Neutron-physical characteristics modeling of light water reactors critical corium slurry in water

CORIUMSITY program code for the consequences analysis of a severe core melt accident

Contact Info

Product

Resources

About