Reactor Pressure Vessel

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

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

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

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 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

The most important ageing effect on the reactor pressure vessel (RPV) is radiation embrittlement, which is mainly caused by fast neutrons during operation lifetime of nuclear reactors. The aim of this study was to investigate the DPA (displacement per atom) rate, an important parameter describing radiation damage to the RPV, and identify the position of the maximum DPA rate in the RPV of the VVER-1000/V320 reactor using the Monte Carlo code MCNP5.

10p vineptune2711 04-11-2019 10 0   Download

The management of hydrogen safety and prevention of overpressurization could be implemented through a hydrogen reduction system and spray system. During the course of the hypothetical large break loss-of-coolant accident in a nuclear power plant, hydrogen is generated by a reaction between steam and the fuel-cladding inside the reactor pressure vessel and also core concrete interaction after ejection of melt into the cavity.

10p minhxaminhyeu5 30-06-2019 17 0   Download

In the present study, several key factors related to molten corium behaviors and thermal characteristics were examined under multi-layered corium formation conditions. Thereafter, systematic finite element analyses and subsequent damage evaluation with varying parameters were performed on a representative reactor pressure vessel (RPV) to figure out the possibility of high temperature induced failures.

11p minhxaminhyeu5 30-06-2019 12 1   Download

The precise prediction of radiation embrittlement of aged reactor pressure vessels (RPVs) is a prerequisite for the long-term operation of nuclear power plants beyond their original design life. The expiration of the operation licenses for Korean reactors the RPVs of which are made from SA533B-1 plates and welds is imminent. Korean regulatory rules have adopted the US Nuclear Regulatory Commission's transition temperature shift (TTS) models to the prediction of the embrittlement of Korean reactor pressure vessels.

4p minhxaminhyeu4 26-06-2019 15 0   Download

Self-pressurization analysis of the natural circulation integral nuclear reactor through a new dynamic model is studied. Unlike conventional pressurized water reactors, this reactor type controls the system pressure using saturated coolant water in the steam dome at the top of the pressure vessel. Selfpressurization model is developed based on conservation of mass, volume, and energy by predicting the condensation that occurs in the steam dome and the flashing inside the chimney using the partial differential equation.

11p minhxaminhyeu3 25-06-2019 20 1   Download

State the mechanism for steam generation in a PWR. Using simplified diagrams, identify and explain the purpose of the major components and equipment involved with a PWR. Identify the equipment used to control reactor power.

24p giotletinh_hd2009 14-10-2013 84 8   Download

In BWR’s steam bubbles have a negative steam bubbles have a negative reactivity feedback, if the steam fraction reactivity feedback, if the steam fraction increases in the core the reactor power increases in the core the reactor power decreases

34p tieunhan202 07-10-2013 54 6   Download

In this section, the hydrodynamics of a dual fluidized beds has been discussed using the almost similar system as described in (Loffler et al. 2003; Kaiser et al., 2003) except the mechanism for the solids transfer between the vessels. Loop seal device has been used in the studies described in (Loffler et al. 2003; Kaiser et al., 2003). In the current study, two L- valves, in place of loop seals, have been installed between the coupled reactors. The L-valves absorb a part of pressure that is built up due to static head of solids in the downcomer. Depending upon the pressure...

250p contentnew 12-04-2012 125 24   Download