Measurement of 232Th(n,γ)233Th, 98Mo(n,γ)99Mo, 186W(n,γ) 187W, 115In(n,γ)116ml In, and 92Mo(n,p)92mNb Cross Sections in the Energy Range of 1.6 to 3.7 MeV

被引:9
作者
Bhike, Megha [1 ]
Roy, B. J. [1 ]
Saxena, A. [1 ]
Choudhury, R. K. [1 ]
Ganesan, S. [2 ]
机构
[1] Bhabha Atom Res Ctr, Div Nucl Phys, Bombay 400085, Maharashtra, India
[2] Bhabha Atom Res Ctr, Reactor Phys Design Div, Bombay 400085, Maharashtra, India
关键词
FAST-NEUTRON CAPTURE; RADIATIVE-CAPTURE; EXCITATION-FUNCTIONS; NUCLEAR-SCIENCE; ALPHA REACTIONS; MODEL; SCATTERING; THRESHOLD; LIBRARY;
D O I
10.13182/NSE10-63
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-induced. reaction cross sections for the reaction Th-232(n, y)Th-233 have been measured at neutron energies of 1.6 +/- 0.03 MeV, 2.2 +/- 0.03 MeV, 3.0 +/- 0.03 MeV, and 3.7 +/- 0.03 MeV. We have also measured cross sections for the reactions Mo-98(n, y)Mo-99, W-186(n, y) W-187, (115) In(n, y)(116ml) In, and Mo-92(n, p)Nb-92m at a neutron energy of 3.2 +/- 0.03 MeV. The (7) Li( p, n)(7) Be reaction was used as the neutron source with the proton beam from the 14-MV Pelletron accelerator, Mumbai, and the standard off-line gamma counting method was followed for activation measurement. The present measurements supplement the existing data and provide new data in the neutron energy range where no results are available. While the cross-section values for the Mo-98(n, y)Mo-99 and W-186(n, y)W-187 reactions are reported for the first time, the data for Mo-92(n, p)Nb-92m exists with a large discrepancy between the two available data sets. For the In-115(n, y)(116ml) In reaction, our measurement at 3.2 MeV is an additional data point where there exists significant disagreement among the data measured by different groups. The measurements are performed relative to the (115) In(n,n')(115m) In and Au-197(n, y)Au-198 cross sections of International Reactor Dosimetry File 2002. Detailed theoretical calculations using the statistical model code EMPIRE-II (latest version EMPIRE-2.19) have been performed. Good agreement with the present data along with the existing data set has been obtained by suitable adjustment of the level density parameter for all the systems. The experimental and theoretical results have been compared with the recent evaluations of ENDF/B-VII.0, JENDL-4.0, and JEFF-3.1.
引用
收藏
页码:44 / 53
页数:10
相关论文
共 58 条
[21]   STATISTICAL MODEL OF INTERMEDIATE STRUCTURE [J].
GRIFFIN, JJ .
PHYSICAL REVIEW LETTERS, 1966, 17 (09) :478-&
[22]  
HANNA R. C., 1959, NUCL ENERGY, V8, P197
[23]   NEUTRON-SCATTERING CROSS-SECTIONS FOR TH-232,U-233,U-235,U-238,PU-239 AND PU-242 BETWEEN 0.6 AND 3.4 MEV [J].
HAOUAT, G ;
LACHKAR, J ;
LAGRANGE, C ;
JARY, J ;
SIGAUD, J ;
PATIN, Y .
NUCLEAR SCIENCE AND ENGINEERING, 1982, 81 (04) :491-511
[24]   EMPIRE: Nuclear reaction model code system for data evaluation [J].
Herman, M. ;
Capote, R. ;
Carlson, B. V. ;
Oblozinsky, P. ;
Sin, M. ;
Trkov, A. ;
Wienke, H. ;
Zerkin, V. .
NUCLEAR DATA SHEETS, 2007, 108 (12) :2655-2715
[25]  
HERMAN M., 2010, STAT MODEL CODE EMPI
[26]   ABSOLUTE NEUTRON CROSS-SECTION MEASUREMENTS IN THE ENERGY-RANGE BETWEEN 2 AND 5 MEV [J].
HUSSAIN, HA ;
HUNT, SE .
INTERNATIONAL JOURNAL OF APPLIED RADIATION AND ISOTOPES, 1983, 34 (04) :731-738
[27]  
IGNATYUK AV, 1979, SOV J NUCL PHYS+, V29, P450
[28]  
IGNATYUK AV, COMMUNICATION
[29]   ENERGY DEPENDENCE OF FAST-NEUTRON ACTIVATION CROSS SECTIONS [J].
JOHNSRUD, AE ;
SILBERT, MG ;
BARSCHALI, HH .
PHYSICAL REVIEW, 1959, 116 (04) :927-936
[30]  
JOLY S., 1981, 5089 CTR ET NUCL