KP1 acceleration scheme for inner iterations consistent with the weighted diamond differencing scheme for the transport equation in three-dimensional geometry

Voloshchenko, A. M.

doi:10.1134/s0965542509020134

Cited by 6 publications

(2 citation statements)

References 12 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…Для вычисле ния сечений реакций используется модуль Groups [14] и дозиметрическая библио тека IRDFF [15]. В (r, z) геометрии расчеты выполняются на персональном компьютере по про грамме КАСКАД [16] с использованием AWDD схемы с кусочно постоянным представ лением решения в ячейке [17]. В (x, y, z) геометрии расчеты выполняются по про грамме РадугаТ [18] по ThetraLc схеме с кусочно линейным представлением реше ния [19].…”

Section: моделирование экспериментаunclassified

Detailed simulation of winfrith IRON 88 benchmark (ASPIS) IN (r, z)- and (x, y, z)-geometries

Nikolaeva

Gaifulin

Bass

2019

YadEn

View full text Add to dashboard Cite

show abstract

Section: моделирование экспериментаunclassified

Detailed simulation of winfrith IRON 88 benchmark (ASPIS) IN (r, z)- and (x, y, z)-geometries

Nikolaeva

Gaifulin

Bass

2019

YadEn

View full text Add to dashboard Cite

show abstract

“…Three-dimension (R--Z) neutron transport computations were carried out in the P 3 S 16 approximation of the discrete ordinates method using the KATRIN-2.5 [5][6][7][8][9][10] code with 47-groups nuclear data library BGL-1000 based on the ENDF-B/VI data.…”

Section: Measurements and Calculation Proceduresmentioning

confidence: 99%

Changes to Irradiation Conditions of VVER-1000 Surveillance Specimens Resulting from Fuel Assemblies with Greater Fuel Height

Panferov

Kochkin

Erak

et al. 2016

EPJ Web of Conferences

View full text Add to dashboard Cite

Abstract. The goal of the work was to obtain experimental data on the influence of newtype fuel assemblies with higher fuel rods on the irradiation conditions of surveillance specimens installed on the baffle of VVER-1000. For this purpose, two surveillance sets with container assemblies of the same design irradiated in reactors with different fuel assemblies in the core were investigated. Measurements of neutron dosimeters from these sets and retrospective measurements of 54 Mn activity accumulated in each irradiated specimen allow a detailed distribution of the fast neutron flux in the containers to be obtained. Neutron calculations have been done using 3D discrete ordinate code KATRIN. On the basis of the obtained results, a change of the lead factor due to newtype fuel assemblies was evaluated for all types of VVER-1000 container assemblies.

show abstract

An iterative KP1 method for solving the transport equation in 3D domains on unstructured grids

Kokonkov

Николаева

2015

Comput. Math. and Math. Phys.

View full text Add to dashboard Cite

KP1 acceleration scheme for inner iterations consistent with the weighted diamond differencing scheme for the transport equation in three-dimensional geometry

Cited by 6 publications

References 12 publications

Detailed simulation of winfrith IRON 88 benchmark (ASPIS) IN (r, z)- and (x, y, z)-geometries

Detailed simulation of winfrith IRON 88 benchmark (ASPIS) IN (r, z)- and (x, y, z)-geometries

Changes to Irradiation Conditions of VVER-1000 Surveillance Specimens Resulting from Fuel Assemblies with Greater Fuel Height

An iterative KP1 method for solving the transport equation in 3D domains on unstructured grids

Contact Info

Product

Resources

About