Gamma-ray spectrometry analysis of pebble bed reactor fuel using Monte Carlo simulations

被引:13
作者
Chen, JW
Hawari, AI [1 ]
Zhao, ZX
Su, BJ
机构
[1] Univ Cincinnati, Nucl & Radiol Engn Program, Cincinnati, OH 45221 USA
[2] N Carolina State Univ, Dept Nucl Engn, Raleigh, NC 27695 USA
关键词
pebble bed reactor; burnup; fuel; gamma ray; spectrometry; Monte Carlo; germanium detector;
D O I
10.1016/S0168-9002(03)01105-7
中图分类号
TH7 [仪器、仪表];
学科分类号
0804 ; 080401 ; 081102 ;
摘要
Monte Carlo simulations were used to study the gamma-ray spectra of pebble bed reactor fuel at various levels of burnup. A fuel depletion calculation was performed using the ORIGEN2.1 code, which yielded the gamma-ray source term that was introduced into the input of an MCNP4C simulation. The simulation assumed the use of a 100% efficient high-purity coaxial germanium (HPGe) detector, a pebble placed at a distance of 100 cm from the detector, and accounted for Gaussian broadening of the gamma-ray peaks. Previously, it was shown that Cs-137, Co-60 (introduced as a dopant), and Cs-134 are the relevant burnup indicators. The results show that the 662 keV line of Cs-137 lies in close proximity to the intense 658 keV of Nb-197, which results in spectral interference between the lines. However, the 1333 keV line of Co-60, and selected Cs-134 lines (e.g., at 605 keV) are free from spectral interference, which enhances the possibility of their utilization as relative burnup indicators. (C) 2003 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:393 / 396
页数:4
相关论文
共 5 条
[1]  
Briesmeister J.F., 2000, LA13709M LOS AL NAT
[2]  
Croff A.G., 1980, USERS MANUAL ORIGEN2
[3]  
Gittus JH, 1999, NUCL ENERG-J BR NUCL, V38, P215
[4]  
HAWARII AI, IN PRESS IEEE T NUCL
[5]  
HENSLEY WK, 1993, P IEEE NSS MIC, V1, P672