Assessing reactor physics codes capabilities to simulate fast reactors on the example of the BN-600 Benchmark

Kerntechnik ◽  
2016 ◽  
Vol 81 (5) ◽  
pp. 512-519 ◽  
Author(s):  
V. Ivanov ◽  
J. Bousquet
2019 ◽  
Vol 34 (2) ◽  
pp. 122-128
Author(s):  
Hui Ding ◽  
Quan Gan ◽  
Lijuan Hao ◽  
Jing Song ◽  
Yican Wu

Lead-cooled fast reactors have multilayered designs and large internal temperature differences, which cause challenges in simulating reactor physics. SuperMC, a large-scale integrated software system for neutronics design, is inherently able to address complex geometries and multi-temperature problems. The purpose of this study is to verify the applicability of SuperMC to the lead-bismuth-cooled fast reactor RBEC-M. The multi-temperature cross-section generation function of SuperMC was employed and showed good performance. Based on the ENDF/B-VII.1 library, the effective multiplication factor keff obtained by SuperMC showed good agreement with those from previous works. The relationship of keff and 15N enrichment applied to the fuel material was also studied, with the results showing that in creased 15N could significantly improve keff. The axial power profile and kinetics parameters for the bench mark were then calculated and analyzed. This work thus verified the applicability of SuperMC for comprehensive neutronics simulations for lead-bismuth-cooled fast reactors.


2007 ◽  
pp. 48-62 ◽  
Author(s):  
L. Buiron ◽  
Ph. Dufour ◽  
G. Rimpault ◽  
G. Prulhiere ◽  
C. Thevenot ◽  
...  
Keyword(s):  

2019 ◽  
Vol 12 (4) ◽  
pp. 50-61
Author(s):  
А. Harutyunyan ◽  
S.B. Vygovskiy ◽  
A. Khachatryan

2017 ◽  
Author(s):  
Chad L. Pope ◽  
◽  
Edward S Lum ◽  
Ryan Stewart ◽  
Bilguun Byambadorj ◽  
...  

2016 ◽  
Vol 2 ◽  
pp. 14 ◽  
Author(s):  
Benjamin A. Lindley ◽  
Dan Kotlyar ◽  
Geoffrey T. Parks ◽  
John N. Lillington ◽  
Bojan Petrovic
Keyword(s):  

Atomic Energy ◽  
2021 ◽  
Author(s):  
N. V. Gorin ◽  
N. P. Voloshin ◽  
Yu. I. Churikov ◽  
A. N. Chebeskov ◽  
V. P. Kuchinov ◽  
...  

Energies ◽  
2021 ◽  
Vol 14 (15) ◽  
pp. 4610
Author(s):  
Ahmed Amin E. Abdelhameed ◽  
Chihyung Kim ◽  
Yonghee Kim

The floating absorber for safety at transient (FAST) was proposed as a solution for the positive coolant temperature coefficient in sodium-cooled fast reactors (SFRs). It is designed to insert negative reactivity in the case of coolant temperature rise or coolant voiding in an inherently passive way. The use of the original FAST design showed effectiveness in protecting the reactor core during some anticipated transients without scram (ATWS) events. However, oscillation behaviors of power due to refloating of the absorber module in FAST were observed during other ATWS events. In this paper, we propose an improved FAST device (iFAST), in which a constraint is imposed on the sinking (insertion) limit of the absorber module in FAST. This provides a simple and effective solution to the power oscillation problem. Here, we focus on an oxide fuel-loaded SFR that is characterized by a more negative Doppler reactivity coefficient and higher operating temperature than the metallic-loaded SFR cores. The study is carried out for the 1000 MWth advanced burner reactor with an oxide fuel-loaded core during postulated ATWS events that are unprotected transient over power, unprotected loss of flow, and unprotected loss of the heat sink. It was found that the iFAST device has promising potentials for protecting the oxide SFR core during the various studied ATWS events.


Sign in / Sign up

Export Citation Format

Share Document