Analysis of the reactivity coefficients and fuel burnup for MNSR research reactor using DRAGON5/DONJON5 codes

2019 ◽  
Vol 160 ◽  
pp. 56-62
Author(s):  
Jamal Al Zain ◽  
O. El Hajjaji ◽  
T. El Bardouni ◽  
Afaf El Mtili
2017 ◽  
Vol 860 ◽  
pp. 012033 ◽  
Author(s):  
S Sangkaew ◽  
T Angwongtrakool ◽  
B Srimok

Author(s):  
Md. Mizanur Rahman ◽  
Anisur Rahman ◽  
Shafiul Hossain ◽  
P.K. Das ◽  
Md. Ashraf Ali ◽  
...  
Keyword(s):  

2016 ◽  
Vol 3 (1) ◽  
Author(s):  
Michal Koleška ◽  
Michal Šunka ◽  
Jaroslav Ernest

A spectrometric system was developed for spent fuel burnup evaluations at the LVR-15 research reactor, which employed highly enriched (36%) IRT-2M-type fuel. Such a system allows the measurement of fission product axial distribution by measuring certain nuclides, such as Cs137, Cs134, and their ratios, respectively. Within the paper, a comparison between experimental data provided by the spectrometric system and calculations in operational code called NODER is provided.


2015 ◽  
Vol 2 (1) ◽  
Author(s):  
Csaba Maráczy ◽  
György Hegyi ◽  
István Trosztel ◽  
Emese Temesvári

The aim of the supercritical water reactor-fuel qualification test (SCWR-FQT) Euratom-China collaborative project is to design an experimental facility for qualification of fuel for the supercritical water-cooled reactor. The facility is intended to be operated in the LVR-15 research reactor in the Czech Republic. The pressure tube of the FQT facility encloses four fuel rods that will operate in similar conditions to the evaporator of the HPLWR reactor. This article deals with the three-dimensional (3D) coupled neutronic-thermohydraulic steady-state and transient analysis of LVR-15 with the fueled loop. Conservatively calculated enveloping parameters (e.g., reactivity coefficients) were determined for the safety analysis. The control rod withdrawal analysis of the FQT facility with and without reactor SCRAM was carried out with the KIKO3D-ATHLET-coupled dynamic code.


2018 ◽  
Vol 29 (12) ◽  
Author(s):  
Quang Binh Do ◽  
Hoai-Nam Tran ◽  
Quang Huy Ngo ◽  
Giang T. T. Phan
Keyword(s):  

2020 ◽  
Vol 6 (2) ◽  
pp. 99-104 ◽  
Author(s):  
Tuul Baatar ◽  
Evgeny G. Kulikov

Increasing fuel burnup is one of the important areas of nuclear power development. Currently, the most common type of light-water reactors is characterized by burnup ratios of about 5%, i.e., only a small fraction of fuel is used to generate electricity. The paper considers the possibility of a significant increase in fuel burnup due by introducing protactinium and neptunium into the fuel composition. The chains of nuclide transformations starting with protactinium and neptunium are characterized by a gradual improvement in the multiplying properties, which ensures increased fuel burnup. At the same time, a situation may be observed when the multiplying properties of a fuel composition are improved during the campaign, which indicates that at a certain point in time the accumulation rate of fissile nuclides from protactinium and neptunium exceeds the accumulation rate of fission products. While protactinium is hardly accessible in sufficient quantities, neptunium is contained in spent nuclear fuel, a significant amount of which is stored in on-site facilities. Therefore, from a practical perspective, the introduction of neptunium into fuel compositions seems to be more preferable. The novelty of the work is the analysis of the effects of protactinium and neptunium on the reactivity coefficients during fuel campaigns. The calculations were carried out for a VVER-1000 type reactor using the SCALE-6.2 software package.


2014 ◽  
pp. 14-18
Author(s):  
Yu. Ovdiienko ◽  
M. Yeremenko ◽  
V. Khalimonchuk ◽  
A. Kuchin ◽  
Yu. Bilodid

In preparation of few-group cross-section libraries to be used in WWER macro-calculations, change in the nuclide composition during fuel burnup is commonly defined under invariable characteristics, averaged over the entire core (power, fuel and moderator temperature, moderator density etc.). In reality, conditions of fuel burnup are changing and this factor affects the fuel nuclide composition (the so-called spectral history effect). To account for real burnup history, it is necessary to take into consideration the dependence of cross-sections not only on burnup but also on history of neutron spectrum in the fuel burnup process. This paper analyzes fuel burnup history effect on neutronic characteristics of WWER-1000 core with use of the DYN3D code. The DYN3D code employs the local Pu-239 concentration as an indicator of burnup spectral history. The calculations have been performed for the first four fuel loadings of Khmelnitsky NPP unit 2 and stationary fuel loading with TVSA. The effect of fuel burnup history is shown both on macro-characteristics of the reactor core (boric acid concentration, fuel cycle duration, reactivity coefficients) and on local values of burnup and power.


2018 ◽  
Vol 11 ◽  
pp. 564-569 ◽  
Author(s):  
Saadou Aldawahrah ◽  
S. Dawahra ◽  
K. Khattab ◽  
G. Saba ◽  
M. Boush

Sign in / Sign up

Export Citation Format

Share Document