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Light Water Reactor
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Studies on modeling uranium dioxide (UO2) powder and pellet processes from ammonium uranyl carbonate (AUC)- derived uranium dioxide powder (UO2 ex-AUC powder) were reported in the paper.
14p
vicedric
08-02-2023
7
3
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The results of this analysis showed that comparing to other transients, a large break LOCA lead to the most severe pressurized thermal shock conditions, while the risk of SOV transients are strongly related to the re-pressurization in the pressurizer caused by the increase of water level due to the relief valve stuck open.
6p
vicedric
08-02-2023
6
2
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Studies on modeling uranium dioxide (UO2) powder and pellet processes from ammonium diuranate (ADU)- derived uranium dioxide powder (UO2 ex-ADU powder) were reported in the paper. A mathematical model describing the effect of the fabrication parameters on specific surface area (SSA) of UO2 powders was built up.
12p
vidumbledore
06-01-2023
10
2
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The nonlinear stability analysis of a supercritical light water reactor (SCLWR) is presented using a nuclearcoupled thermal-hydraulic reduced-order model. The analytical model is developed by coupling 1. the pointkinetics equations with one group of delayed neutrons, 2. the fuel heat transfer and 3. a 1-D reduced order model which represents the heat absorption phenomenon during the coolant flow.
20p
vironald
15-12-2022
15
5
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The Virtual Environment for Reactor Applications (VERA) core physics benchmark problem #6, 3D Hot Full Power (HFP) assembly, from the Consortium for Advanced Simulation of Light Water Reactors (CASL) was simulated using the MC21 continuous energy Monte Carlo code coupled with the COBRA-IE subchannel thermal-hydraulics code using the R5EXEC coupling framework.
14p
vironald
15-12-2022
7
4
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A simulation-based study concerning three non-destructive approaches by which water in spent nuclear fuel assemblies might be quantified with neutrons is described. Three fuel types have been considered: thirty-six spent Advanced Gas-cooled Reactor (AGR) fuel pins contained in a stainless-steel can; a prototype fast reactor (PFR) spent fuel assembly and a light water reactor (LWR) spent fuel assembly – with the PFR and LWR assemblies containing mixed oxide fuels.
25p
vironald
15-12-2022
13
4
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SuperCritical Water Reactor(SCWR) applies water beyond the thermodynamic critical point as the coolant, which aims to achieve high efficiency around 45% compared to 33% for existing commercial light water reactors.
15p
vironald
15-12-2022
11
4
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The preferred method for disposal of used nuclear fuel is underground emplacement in a Deep Geological Repository (DGR). Many countries have light water reactor fuels which require large Used Fuel Container or Canister (UFC) designs weighing up to 25 ton for containment.
10p
vironald
15-12-2022
11
4
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In view of the potential deployment of demonstrators and prototypes associated with the European Sustainable Nuclear Industrial Initiative (ESNII), the present licensing framework, based on the current Light Water Reactor (LWR) technology, will have to adjust as necessary taking into account to the new safety aspects introduced by these innovative technologies.
15p
vironald
15-12-2022
12
4
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CANDU (CANada Deuterium Uranium) reactors have many unique design features that play important roles during a severe accident, however analysis of such features using Light Water Reactor (LWR) specific computer codes is challenging.
23p
vironald
15-12-2022
11
3
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The design and testing of an irradiation rig using flux screen method for NTD-Si at the DNRR are necessary to have a better understanding and experience in NTD-Si application. The new irradiation rig using various screen materials (stainless steel, aluminum and light water) was designed, installed and tested in the core of DNRR.
8p
trinhthamhodang1218
14-03-2021
9
1
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This paper will provide an update on results from the feasibility study and discuss the attributes of the coated Mo cladding design to meet the challenging requirements for improving fuel tolerance to severe loss of coolant accidents.
6p
christabelhuynh
30-05-2020
15
2
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The contribution of the thermal scattering law of hydrogen in light water to isothermal temperature reactivity coefficients for UOX and MOX lattices was studied in the frame of the MISTRAL critical experiments carried out in the zero power reactor EOLE of CEA Cadarache (France).
15p
christabelhuynh
30-05-2020
9
1
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The purpose of this study is to investigate the relevance of U5-FRs in a nuclear fleet deployment configuration. Considering several power demand scenarios and assuming different finite quantities of available natural uranium, this paper examines what types of reactors must be deployed to meet the demand.
10p
christabelhuynh
30-05-2020
18
0
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In this document, we present a simplified geometrical model (0D model) for the in-core corium propagation transient. A degraded core with a formed corium pool is used as an initial state. This state can be obtained from a simulation computed with an integral code.
9p
christabelhuynh
30-05-2020
5
0
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A correlated sampling technique has been implemented to estimate the impact of cross section modifications on the neutron transport and in Monte Carlo simulations in one single calculation. This implementation has been coupled to a Total Monte Carlo approach which consists in propagating nuclear data uncertainties with random cross section files.
9p
christabelhuynh
29-05-2020
5
0
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In the current paper, we investigate the application of the Equivalent Generalized Perturbation Theory (EGPT) to derive trends and associated covariances on the neutron capture cross section of one major fission product for both light water reactors and sodium-cooled fast reactors which is Rhodium-103.
9p
christabelhuynh
29-05-2020
12
0
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Objectives of research: Research on ammonia removal in groundwater in Hanoi with the concentration of less than 25mg/L (20mgN/L) by simultaneous Nitrification and Denitrification process in the equipment using MBBR with porous carriers (DHY) of a high surface area of about 6,000-8,000 m2 /m3 , high porosity and light weight, easily moving in water without addition of substrates.
26p
xacxuoc4321
09-07-2019
25
5
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The results showed a strong correlation between the load and the premixed mass, defined as the mass of the molten material in low void zones (void fraction < 0.75). The jet diameter and velocity that comprise the flow rate were the primary factors to determine the premixed mass and the load.
8p
minhxaminhyeu5
30-06-2019
10
1
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The fast neutron spectrum allows up to a ~30-fold gain in fuel utilization efficiency when compared to conventional light water reactors utilizing enriched fuel. When compared to other fast reactors, TWRs represent the lowest cost alternative to enjoy the energy security benefits of an advanced nuclear fuel cycle without the associated proliferation concerns of chemical reprocessing.
14p
minhxaminhyeu5
30-06-2019
17
0
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