Experimental neutron attenuation measurements in possible fast reactor shield materials

被引:14
|
作者
Nyarku, Mawutorli [1 ,2 ]
Keshavamurthy, Ramanathapura S. [1 ]
Subramanian, Venkata D. [1 ]
Haridas, Adish [1 ]
Glover, Eric T. [2 ]
机构
[1] Indira Gandhi Ctr Atom Res, Reactor Shielding & Data Div, Reactor Phys Grp, Kalpakkam 603102, Tamil Nadu, India
[2] Ghana Atom Energy Commiss, Natl Nucl Res Inst, Legon, Ghana
关键词
KAMINI Reactor; Neutron attenuation; Shield material; Activation foil;
D O I
10.1016/j.anucene.2012.10.019
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
Neutron attenuation properties of shield materials that have prospective use in fast reactors have been studied in this research. Activation foils were employed to study neutron attenuation behavior of Ferro tungsten powder and mild steel slabs in the south neutron beam end of KAMINI Reactor. The results reveal that epithermal neutron attenuation in Ferro tungsten is better than in mild steel from plots of attenuation versus areal density and attenuation versus areal atom density. Fast neutron attenuation in Ferro tungsten is comparable to mild steel from plot of attenuation versus areal density. Ferro tungsten however shows higher fast neutron attenuation in plot of attenuation versus areal atom density. It can be deduced that, Ferro tungsten would be a better neutron attenuator compared to steel if its bulk density is increased. Ferro tungsten would therefore not only be an effective shield material than steel but a better substitute for steel in high temperature applications. (C) 2012 Elsevier Ltd. All rights reserved.
引用
收藏
页码:135 / 139
页数:5
相关论文
共 50 条
  • [1] Experimental Measurements of Neutron Attenuation in the Advanced Shield Material Ferro Boron in KAMINI Reactor
    Keshavamurthy, R. S.
    Subramanian, D. Venkata
    Prasad, Rajeev Ranjan
    Haridas, Adish
    Mohanakrishnan, P.
    Chetal, S. C.
    ASIAN NUCLEAR PROSPECTS 2010, 2011, 7 : 273 - 278
  • [2] NEUTRON FLUX IN SHIELD OF DOUNREAY FAST REACTOR
    ADAMSON, J
    JUDD, AM
    MCNAIR, NI
    JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1965, 4 (02): : 119 - &
  • [3] A FAST NEUTRON SPECTROMETER FOR REACTOR FLUX MEASUREMENTS
    FURR, AK
    RUNYON, RS
    NUCLEAR INSTRUMENTS & METHODS, 1964, 27 (03): : 292 - 298
  • [4] FAST-REACTOR NEUTRON ABSORBER MATERIALS
    MAHAGIN, DE
    AMERICAN CERAMIC SOCIETY BULLETIN, 1979, 58 (03): : 393 - 393
  • [5] ATTENUATION MEASUREMENTS OF A FAST-NEUTRON RADIOTHERAPY BEAM
    ATTIX, FH
    THEUS, RB
    MILLER, GE
    PHYSICS IN MEDICINE AND BIOLOGY, 1976, 21 (04): : 530 - 543
  • [6] MEASUREMENTS OF FAST-NEUTRON SPECTRA IN REACTOR SHIELDS
    LIVENGOOD, CD
    PAULSON, CK
    HUNGERFORD, HE
    NUCLEAR SCIENCE AND ENGINEERING, 1973, 52 (02) : 254 - 266
  • [7] Measurements and calculations of neutron flux and dose rates for an experimental epithermal facility at the TAPIRO fast reactor
    Gambarini, G
    Colombi, C
    Lietti, B
    Agosteo, S
    Burn, KW
    Nava, E
    Tinti, R
    Fiorani, O
    Perrone, A
    Rosi, G
    RESEARCH AND DEVELOPMENT IN NEUTRON CAPTURE THERAPY, 2002, : 367 - 371
  • [8] FAST-NEUTRON SHIELD ANALYSIS FOR PRESSURIZED WATER-REACTOR VESSELS
    TRAN, KC
    TURNER, RL
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1984, 47 : 379 - 381
  • [9] Shielding experiments for optimization of shield materials in fast reactor using SSNTDs
    Kolekar, R. V.
    Kumar, R.
    Sharma, D. N.
    INDIAN JOURNAL OF PHYSICS, 2013, 87 (06) : 581 - 585
  • [10] Shielding experiments for optimization of shield materials in fast reactor using SSNTDs
    R V Kolekar
    R Kumar
    D N Sharma
    Indian Journal of Physics, 2013, 87 : 581 - 585