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
Keyword(s):  
Fast Reactors ◽  
Reactor Physics

scholarly journals Verification and application of SuperMC3.3 to lead-bismuth-cooled fast reactor

2019 ◽  
Vol 34 (2) ◽  
pp. 122-128
Author(s):  
Hui Ding ◽  
Quan Gan ◽  
Lijuan Hao ◽  
Jing Song ◽  
Yican Wu
Keyword(s):  
Fast Reactor ◽  
Large Scale ◽  
Bench Mark ◽  
Fast Reactors ◽  
Reactor Physics ◽  
Kinetics Parameters ◽  
Power Profile ◽  
Integrated Software ◽  
Relationship Of ◽  
The Relationship

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.

Innovative Core Design for Generation IV Sodium-Cooled Fast Reactors

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

Study Ways to Increase KW in Fast Reactors with MOX Fuel Aiming for the Minimum of Sodium Void Reactivity Effect

2019 ◽  
Vol 12 (4) ◽  
pp. 50-61
Author(s):  
А. Harutyunyan ◽  
S.B. Vygovskiy ◽  
A. Khachatryan
Keyword(s):  
Fast Reactors ◽  
Reactivity Effect ◽  
Mox Fuel

EBR-II Reactor Physics Benchmark Evaluation Report

2017 ◽  
Author(s):  
Chad L. Pope ◽  
◽  
Edward S Lum ◽  
Ryan Stewart ◽  
Bilguun Byambadorj ◽  
...  
Keyword(s):  
Reactor Physics ◽  
Evaluation Report ◽  
Benchmark Evaluation

scholarly journals Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes

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

Nuclear Non-Proliferation Security on Exportation of Fast Reactors with a Closed Fuel Cycle

Atomic Energy ◽  
2021 ◽  
Author(s):  
N. V. Gorin ◽  
N. P. Voloshin ◽  
Yu. I. Churikov ◽  
A. N. Chebeskov ◽  
V. P. Kuchinov ◽  
...  
Keyword(s):  
Fuel Cycle ◽  
Fast Reactors ◽  
Closed Fuel Cycle

scholarly journals Improved FAST Device for Inherent Safety of Oxide-Fueled Sodium-Cooled Fast Reactors

Energies ◽  
2021 ◽  
Vol 14 (15) ◽  
pp. 4610
Author(s):  
Ahmed Amin E. Abdelhameed ◽  
Chihyung Kim ◽  
Yonghee Kim
Keyword(s):  
Operating Temperature ◽  
Reactor Core ◽  
Coolant Temperature ◽  
Inherent Safety ◽  
Oxide Fuel ◽  
Fast Reactors ◽  
Power Oscillation ◽  
Negative Reactivity ◽  
Oscillation Problem ◽  
Reactivity Coefficient

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.

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