International Reactor Innovation and Secure (IRIS) is one of the next generation nuclear plant designs with significant advances in safety, operation performance, and proliferation resistance. The Helical Coil Steam Generator (HCSG) constitutes a critical contributor to the integral primary system design of the IRIS reactor. However, the integral design features and the thermal-hydraulic charac...

Nuclear power is a major source of electricity in the international community. However, significant problem with nuclear that, if severe accident occurs, radiation may leak and cause great damage. As such, research on safety has become increasingly popular worldwide. In this paper, structural integrity reactor cavity during steam explosion—one kind aforementioned accidents—was evaluated. Steam ...

This paper presents a generalized likelihood ratio technique for detection of defect locations from bobbin coil eddy current data. First a Neyman±Pearson (NP) decision rule for detection of known random signals (in presence of noise) is discussed. The result is then generalized to the problem of detection of unknown random signals that are commonly found in bobbin coil eddy current data. The pe...

Effect of pseudocritical rapid energy dissipation (PRED) from Pressurizer in nuclear steam supply system Pressurized Water Reactor, where a single event as common cause failure, considerable reduction base-load electricity demand causes the temperature reactor coolant (RCS) to increase, and corresponding pressure increases pressurizer generators above set-points. The study employed uses MATLAB/...

Fault diagnosis is crucial for the operation of energy systems such as nuclear plants, and heavily relies on various types of sensors for temperature, pressure, concentration, etc. Due to the redundancy of sensors in each energy system, the sensor selection scheme can deeply influence the diagnostic efficiency. In this paper, a Boolean network (BN) with its linear representation is proposed for...

In this work, we present the application of exergy analysis in the evaluation of the ethanol steam reforming (ESR) process in a catalytic membrane reactor (CMR) containing Pd-Ag membranes sandwiched by PdRh/CeO2 catalyst to produce fuel cell grade pure hydrogen (no sweep gas). ESR experiments were performed at T=873-923 K and P=4-12 bar. The fuel was a mixture of ethanol and distilled water wit...

Reliable emergency response by human operators is a prerequisite to secure the safety of a nuclear power plant (NPP). There are some events that require prompt operator response to achieve optimal recovery and to maintain the plant within its design basis. Therefore, it is critical to understand the amount of time required to perform an emergency response when designing a NPP and emergency oper...

A sub-channel analysis code is commonly used for evaluating thermal-hydraulic behaviors in a fuel assembly. Since the spatial resolution of “sub-channel” level, can provide more detailed information than conventional one-dimensional nuclear reactor safety code, whose “reactor core” level. To predict behavior, it essential to distribution parameter, which significantly affects void fraction pred...

Efficient simulation of the helical coiled once-through steam generator (H-OTSG) is crucial in design and safety analysis high-temperature gas-cooled reactor (HTGR). The physical property phase transformation water brings great challenges during simulation. properties calculation routine occupies a large part computational time solution process. Thus, thermohydraulic library developed based on ...