Reactor vessel

Part 2 book "Chemical process equipment - Selection and design" includes content: Distillation and gas absortion; extraction and leaching; edsorton and ion eschange; crystallization from solutions and melts; chemical reactors; process vessels.

385p muasambanhan09 12-03-2024 5 1   Download

Part 2 book "Chemical process equipment" includes content: disintegration, agglomeration, and size separation of particulate solids; distillation and gas absorption; extraction and leaching; adsorption and ion exchange; crystallization from solutions and melts; chemical reactors; process vessels; membrane separations; gas solid separations; costs of individual equipment.

453p muasambanhan09 12-03-2024 3 0   Download

Part 2 book "Chemical engineering design - Principles, practice and economics of plant and process design" includes content: Optimization in design; plant design; equipment selection, specification, and design; design of pressure vessels; design of reactors and mixers; separation of fluids; separation columns distillation, absorption, and extraction; specification and design of solids handling equipment; heat transfer equipment; transport and storage of fluids.

782p muasambanhan08 01-03-2024 2 1   Download

This specification covers quenched and tempered vacuum-treated carbon and alloy steel forgings for pressure vessels such as those used in reactor systems. Specifically, it covers forgings for vessel closures, shells, flanges, tube sheets, rings, heads, and similar parts.

9p hth_hn_vn 10-12-2023 10 4   Download

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   Download

This study aims to evaluate the potential for “Containment Bypass” in VVER-1000/V-320 reactor during extended Station Blackout (SBO) scenarios that challenge the tubes by primarily involving a natural circulation of superheated steam inside the piping loop and then induce creep rupture tube failure.

8p visnape 30-01-2023 9 4   Download

In this paper, a new analytical method is developed from original In-Vessel Melt Retention with the aim of predicting heat load from a two-layer stratified molten pool to VVER1000 lower head wall under Station Black-Out (SBO) accident accompanied with reactor vessel external cooling strategy.

16p visnape 30-01-2023 6 4   Download

In the paper, the Station Blackout accident accompanied with IVR implementation has been analyzed for VVER1000/V320 reactor by using MELCOR code 1.8.6. Four SBO scenarios have been proposed for the study, among, two SBO scenarios with long-term high pressure showed that the failure of lower head occurred early due to high pressure and high temperature causing creep-rupture, and the external cooling only delayed the failure of lower vessel.

15p vidumbledore 06-01-2023 23 2   Download

The traditional method to evaluate the feasibility of IVR-ERVC strategy is based on the steady state of the molten pool. But in the early stage, the transient behavior of the molten corium may impose a greater threat to the integrity of the reactor pressure vessel.

7p vironald 15-12-2022 11 5   Download

This study deals with the feasibility study of a new in-vessel core melt retention (IVCMR) strategy capable to extend the coping period in the event of adverse situations, involving the melting of the core. Since Fukushima accident, many studies have been carried out to resolve the severe accident mitigation issues related to the corium stabilization inside and outside the reactor vessel.

8p vironald 15-12-2022 14 5   Download

Residual stress in the welds that attach Control Rod Drive Mechanism nozzles into the upper head of a PWR reactor vessel can influence the vessel’s structural integrity and initiate Primary Water Stress Corrosion Cracking. PWSCC at Alloy 600 CRDM nozzles has caused primary coolant leakage in operating PWRs. We have used Deep Hole Drilling to characterise residual stresses in a PWR vessel head.

9p vironald 15-12-2022 11 3   Download

The International Thermonuclear Experimental Reactor (ITER) Vacuum Vessel Pressure Suppression System (VVPSS) limits the Vacuum Vessel (VV) internal pressure, in case of loss of coolant (LOCA) or other pressurizing accidents from the in-vessel components, to 150 kPa (abs).

14p vironald 15-12-2022 17 3   Download

A miniature integrated nuclear reactor design with gravity independent autonomous circulation (ACMIR) was newly proposed. The reactor core, energy transfer system of Stirling and linear electric motors are integrated in the reactor pressure vessel to achieve high power density and autonomous circulation capability.

8p vironald 15-12-2022 7 3   Download

During a hypothetical severe accident of a Nordic boiling water reactor (BWR), an ex-vessel particulate debris bed is expected to form in the flooded lower drywell due to melt-coolant interactions after vessel failure. The key parameter to evaluate debris bed coolability is the dryout heat flux (DHF) or dryout power density, representing the limit of heat removal capacity by the coolant.

11p vironald 15-12-2022 10 3   Download

Severe accident mitigation technology was developed and evaluated for a small integral reactor of SMART. The containment pressure and hydrogen behavior were analyzed using MELCOR computer code (Sandia National Laboratory, 2018) in the SBO (Station Black Out) sequence, which was selected from PSA (Probabilistic Safety Assessment) results for the SMART.

8p vironald 15-12-2022 20 3   Download

Spray cooling is a versatile technology for various cooling applications involving high surface heat fluxes. Experimental facility was built to study heat transfer performance of an upward multi-nozzle array of water sprays impacting a surface of heated plate made of reactor vessel grade steel.

15p vironald 15-12-2022 9 3   Download

"The journal of Nuclear science and technology - Volume 10/Number 2, 2020" present analysis of in-vessel accident progression in VVER1000 NPP during SBO accident with external reactor vessel cooling method; numerical Investigation of Fluid – Structure Interaction (FSI) on Sodium Leakage Accident at Prototype Fast Breeder Reactor Monju; assessment of nitrogen nutrient sources in aquatic environment of Tuyen Lam subcatchment based on it’s stable isotopes ratio (δ15N-NO3) combined with geochemical parameters...

64p trinhthamhodang1218 14-03-2021 16 2   Download

In this study, the MELCOR v1.8.6 code was utilized to perform an analysis of the in-vessel accident progression in VVER1000 reactor during the Station Black-Out (SBO) accident with and without external reactor vessel cooling (ERVC) strategy.

14p trinhthamhodang1218 14-03-2021 11 2   Download

The capability of eddy current testing (ECT) for the bottom mounted instrumentation (BMI) weld area of reactor vessel in a pressurized water reactor was demonstrated by the developed ECT system and procedure.

8p christabelhuynh 31-05-2020 17 0   Download

This paper describes the benchmark study for deterministic and probabilistic fracture mechanics analyzing the beltline region under PTS by using FAVOR code developed by Oak Ridge National Laboratory. The Monte Carlo method was employed in FAVOR code to calculate the conditional probability of crack initiation.

9p vineptune2711 04-11-2019 7 0   Download