Computational Aspects of Core Neutronics Calculation of Sodium-Cooled Fast Reactor at the Core Destruction Stage

被引：0

作者：

Koltashev, D. A. ^{[1
]}

Mosunova, N. A. ^{[1
]}

Strizhov, V. F. ^{[1
]}

Butov, A. A. ^{[2
]}

Klimonov, I. A. ^{[2
]}

Chukhno, V. I. ^{[2
]}

Usov, E. V. ^{[2
]}

机构：

[1] Russian Acad Sci RAS, Nucl Safety Inst, IBRAE, Moscow, Russia

[2] Russian Acad Sci RAS, Nucl Safety Inst, IBRAE, Novosibirsk Branch, Novosibirsk, Russia

来源：

ATOMIC ENERGY | 2022年 / 132卷 / 04期

关键词：

Computational aspects - Core neutronics - Integrated codes - Neutronic calculations - Neutronics - Operational algorithms - Severe accident;

D O I：

10.1007/s10512-023-00930-7

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The approaches used in the EUCLID/V2 integrated code to calculate the core neutronics of a sodium-cooled fast reactor at the core destruction stage are described. Information is offered about the features of the operational algorithms of the SAFR severe accident module and the DN3D neutronics module. The ability of the integrated code to correctly calculate the processes involving core destruction is shown for an LOC accident.

引用

页码：212 / 218

页数：7

共 50 条

[21] Core neutronics characterization of the GFR2400 Gas Cooled Fast Reactor
Perko, Zoltan
Pelloni, Sandro
Mikityuk, Konstantin
Ktepel, Jiri
Szieberth, Mate
Gaetan, Girardin
Vrban, Branislav
Lueley, Jakub
Cerba, Stefan
Halasz, Mate
Feher, Sandor
Reiss, Tibor
Kloosterman, Jan Leen
Stainsby, Richard
Poette, Christian
PROGRESS IN NUCLEAR ENERGY, 2015, 83 : 460 - 481
[22] A neutronics study for improving the safety and performance parameters of a 3600 MWth Sodium-cooled Fast Reactor
Sun, Kaichao
Krepel, Jiri
Mikityuk, Konstantin
Chawla, Rakesh
ANNALS OF NUCLEAR ENERGY, 2013, 53 : 464 - 475
[23] CURRENT STATUS AND DEVELOPMENT OF CORE CALCULATION METHODOLOGY FOR SODIUM COOLED FAST REACTOR IN MITSUBISHI
Ikeda, Kazumi
Moriwaki, Hiroyuki
Nakazato, Wataru
PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 6, 2011, : 145 - +
[24] Comparative study on neutronics characteristics of a 1500 MWe metal fuel sodium-cooled fast reactor
Ohgama, Kazuya
Aliberti, Gerardo
Stauff, Nicolas E.
Ohki, Shigeo
Kim, Taek K.
PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 2, 2016,
[25] Current status and development of core calculation methodology for sodium cooled fast reactor in Mitsubishi
Mitsubishi FBR systems, Inc., 34-17, Jingumae 2-Chome, Shibuya-ku, Tokyo, 150-0001, Japan
不详
Int Conf Nucl Eng Proc ICONE, (145-154):
[26] A scenario of core disruptive accident for Japan sodium-cooled fast reactor to achieve in-vessel retention
Suzuki, Tohru
Kamiyama, Kenji
Yamano, Hidemasa
Kubo, Shigenobu
Tobita, Yoshiharu
Nakai, Ryodai
Koyama, Kazuya
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2014, 51 (04) : 493 - 513
[27] Experimental studies on metallic fuel relocation in a pin bundle core structure of a sodium-cooled fast reactor
Kim, Taeil
Harbaruk, Dzmitry
Lisowski, Darius
Bremer, Nathan
Farmer, Mitchell
Grandy, Christopher
Chang, Yoon Il
NUCLEAR ENGINEERING AND DESIGN, 2020, 365
[28] OPTIMIZATION OF REFUELING SCHEME OF SODIUM-COOLED FAST-REACTOR CORE USING HEURISTIC ENUMERATION METHOD
KOBAYASHI, Y
KONDO, S
TOGO, Y
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1976, 13 (09) : 471 - 482
[29] GEOMETRY SURVEY ON THE CONVEX SHAPED CORE FOR RECRITICALITY PREVENTION AGAINST CDA IN SODIUM-COOLED FAST REACTOR
Chitose, Keiko
Tachi, Yoshiaki
Wakabayashi, Toshio
Takaki, Naoyuki
PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 1, 2018,
[30] Experimental studies on metallic fuel relocation in a pin bundle core structure of a sodium-cooled fast reactor
Kim, Taeil
Harbaruk, Dzmitry
Lisowski, Darius
Bremer, Nathan
Farmer, Mitchell
Grandy, Christopher
Chang, Yoon Il
Kim, Taeil (tikim@anl.gov), 1600, Elsevier Ltd (365):

← 1 2 3 4 5 →