Analysis of Precooling Injection Transient of Steam Generator for High Temperature Gas Cooled Reactor

consequence analysis of the leakage, ignition and explosion during high pressure sour gas injection process to the oil reservoir

there is no doubt that human being needs to become integrated with industry and industry needs to be progressed, daily. on the other hand, serious events in industrial units specially in oil industries has been shown that such damages and events are industry related ones. the consequence of such events and damages which resulted in chemical and poisoned explosions and loss of life and property ...

High Temperature Gas Cooled Reactors

Design of Chinese Modular High-temperature Gas-cooled Reactor Htr-pm

Modular high-temperature gas-cooled reactor (MHTGR) has distinct advantages in the sense of the inherent safety, economy property, high electricity efficiency, potential usage for hydrogen production, and etc. Chinese design of MHTGR, named as High Temperature Gas-Cooled Reactor-Pebble bed Module (HTR-PM), based on the technology and experiences of the HTR-10, is under the standard design phase...

Adaptive Polynomial Chaos Techniques for Uncertainty Quantification of a Gas Cooled Fast Reactor Transient

Uncertainty quantification plays an increasingly important role in the nuclear community, especially with the rise of Best Estimate Plus Uncertainty methodologies. Sensitivity analysis, surrogate models, Monte Carlo sampling and several other techniques can be used to propagate input uncertainties. In recent years however polynomial chaos expansion has become a popular alternative providing hig...

Tritium Production Analysis and Management Strategies for a Fluoride - salt - cooled High - temperature Test Reactor ( FHTR )

The Fluoride-salt-cooled High-temperature Test Reactor (FHTR) is a test reactor concept that aims to demonstrate the neutronics, thermal-hydraulics, materials, tritium management, and to address other reactor operational and maintenance issues before a commercial Fluoride-salt-cooled High-temperature Reactor (FHR) can be deployed. The MIT Nuclear Systems Design class proposed a design for a 100...