Optimization and evaluation of structural and shielding concrete for IFMIF-DONES

被引:3
作者
Piotrowski, Tomasz [1 ]
Romero, Maria Jose Martinez-Echevarria [2 ]
Prochon, Piotr [1 ]
Alonso, Monica Lopez [2 ]
Michalczyk, Rafal [1 ]
Arvizu-Montes, Armando [2 ]
Ciupinski, Lukasz [1 ]
Jarque, Santiago Becerril [3 ]
Jozefiak, Kazimierz [1 ]
Qiu, Yuefeng [4 ]
Ansorge, Martin [5 ]
Chohan, Hari [6 ]
Wojtkowska, Magdalena [1 ]
机构
[1] Warsaw Univ Technol, Warsaw, Poland
[2] Univ Granada, Granada, Spain
[3] IFMIF DONES Espana, Granada, Spain
[4] Karlsruhe Inst Technol, Karlsruhe, Germany
[5] Czech Acad Sci, Nucl Phys Inst, Rez, Czech Republic
[6] United Kingdom Atom Energy Author, Culham Ctr Fus Energy, Abingdon, Oxon, England
关键词
IFMIF-DONES; Radiation; Shielding; Heavy concrete; Ordinary concrete; Neutron;
D O I
10.1016/j.nme.2024.101597
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 aim of this study was to optimize and evaluate structural and shielding concrete for the IFMIF-DONES building. An ordinary concrete of lime-dolomite aggregate from local sources has been chosen for structural concrete and magnetite aggregate was chosen for heavy-weight radiation shielding. The reference for concrete materials design was the one used in the ITER project. After investigations of raw materials, a group of prebatches were prepared and technical properties - density of compressive strength, were measured. Finally, two compositions have been elaborated - one for structural concrete of density 2.5 g/cm3 and the second for radiation shielding concrete of density 3.9 g/cm3. Then a set of 50 x 50 x 5 cm3 slabs were prepared and sent to the Nuclear Physics Institute of the CAS in the Czech Republic for shielding mock-up experiments. Also the other technical properties like E-modulus, bending strength etc. have been determined. Additionally, radiation shielding efficiency has been calculated based on atomic composition.
引用
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页数:6
相关论文
共 16 条
[1]  
[Anonymous], 2021, Concrete-Specification, Performance, Production and Conformity
[2]  
Barabash V., 2019, ITER_D_VMETZW v1.0
[3]  
Chilton A.B., 1984, PRINCIPLES RAD SHIEL
[4]   Calculation of fast neutron removal cross-sections for some compounds and materials [J].
El-Khayatt, A. M. .
ANNALS OF NUCLEAR ENERGY, 2010, 37 (02) :218-222
[5]   MERCSF-N: A program for the calculation of fast neutron removal cross sections in composite shields [J].
El-Khayatt, A. M. ;
Abdo, A. El-Sayed .
ANNALS OF NUCLEAR ENERGY, 2009, 36 (06) :832-836
[6]  
EN, EN 13790-1 to 19
[7]  
Fischer U., ENS-1.1.5.0- NT-00-R10.
[8]  
Kaplan M.F., 1989, Concrete radiation shielding
[9]   Measurements of the neutron spectra from the p plus Be neutron generator of the NPI CAS [J].
Majerle, Mitja ;
Ansorge, Martin ;
Bem, Pavel ;
Koliadko, Daniil ;
Mrazek, Jaromir ;
Novak, Jan ;
Simeckova, Eva ;
Stefanik, Milan ;
Kostal, Michal ;
Matej, Zdenek ;
Chohan, Haridev ;
Wong, Ocean .
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2023, 1053
[10]   Neutron shielding evaluation of concretes and mortars: A review [J].
Piotrowski, Tomasz .
CONSTRUCTION AND BUILDING MATERIALS, 2021, 277