scholarly journals Prompt-period measurement of the Annular Core Research Reactor prompt neutron generation time

1994 ◽  
Author(s):  
R.L. Coats ◽  
D.G. Talley ◽  
F.R. Trowbridge
2014 ◽  
Vol 29 (4) ◽  
pp. 253-258 ◽  
Author(s):  
Atta Muhammad ◽  
Masood Iqbal ◽  
Tayyab Mahmood

In this study kinetic parameters, effective delayed neutron fraction and prompt neutron generation time have been investigated at different burn-up stages for research reactor's equilibrium core utilizing low enriched uranium high density fuel (U3Si2-Al fuel with 4.8 g/cm3 of uranium). Results have been compared with reference operating core of Pakistan research Reactor-1. It was observed that by increasing fuel burn-up, effective delayed neutron fraction is decreased while prompt neutron generation time is increased. However, over all ratio beff/L is decreased with increasing burn-up. Prompt neutron generation time L in the understudy core is lower than reference operating core of reactor at all burn-up steps due to hard spectrum. It is observed that beff is larger in the understudy core than reference operating core of due to smaller size. Calculations were performed with the help of computer codes WIMSD/4 and CITATION.


Atomic Energy ◽  
1995 ◽  
Vol 79 (6) ◽  
pp. 863-865 ◽  
Author(s):  
A. N. Erykalov ◽  
V. V. Kyz'minov ◽  
Yu. V. Petrov

2013 ◽  
Vol 25 (1) ◽  
pp. 237-240 ◽  
Author(s):  
张良 Zhang Liang ◽  
陈伟 Chen Wei ◽  
赵柱民 Zhao Zhumin ◽  
张信一 Zhang Xinyi ◽  
江新标 Jiang Xinbiao

Author(s):  
Seyed Abolfazl Hosseini ◽  
Naser Vosoughi

In this research, effective delayed neutron fraction (βeff) and neutron generation time (Λ) of the Tehran Research Reactor (TRR) are calculated for different uranium enrichments from 14.84 w/o to 96.56 w/o U235 in two states of the TRR, (cold fuel, clad and coolant temperature of 20 °C; and hot fuel, clad and coolant temperature of 65, 49 and 44 °C, respectively) using the MTR_PC computer code. Comparative analysis shows that both βeff and Λ increase as fuel enrichment decreases. However, variation rate of βeff is not the same in two conditions. βeff in the hot state is larger than those calculated in the cold state when fuel enrichment goes more than 83.91%, while the situation is reverse for enrichment less than that. The obtained neutron generation time shows normal behavior for all different fuel enrichments. The variables involved in kinetics parameters calculations (i.e., neutron fission cross section, fuel enrichment, etc.) are investigated theoretically to confirm the results of calculations in cold and hot states. Variations of βeff and Λ with fuel burnup are studied too.


2016 ◽  
Vol 79 (8) ◽  
pp. 1357-1361 ◽  
Author(s):  
L. Yu. Glukhov ◽  
S. P. Kotkov ◽  
M. S. Kuznetsov ◽  
S. S. Chursin

2019 ◽  
Vol 126 ◽  
pp. 410-418 ◽  
Author(s):  
P. Romojaro ◽  
F. Álvarez-Velarde ◽  
N. García-Herranz

2008 ◽  
Vol 35 (8) ◽  
pp. 1397-1402 ◽  
Author(s):  
S.A.H. Feghhi ◽  
M. Shahriari ◽  
H. Afarideh

2020 ◽  
Vol 194 (12) ◽  
pp. 1116-1127
Author(s):  
Cheol Ho Pyeon ◽  
Masao Yamanaka ◽  
Tomohiro Endo ◽  
Go Chiba ◽  
Willem F. G Van Rooijen ◽  
...  

Sign in / Sign up

Export Citation Format

Share Document