Reactor Design and Safety

Oka, Y.; Morooka, Shigenori

doi:10.1007/978-4-431-55025-9_2

Cited by 3 publications

(4 citation statements)

References 71 publications

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“…ZrH 1.7 moderates fast neutrons produced from the SA in fission, while fertile nuclides in the BA increase neutron absorption to provide negative void reactivity. However, because ZrH 1.7 fuel rods cause fuel peaks between adjacent assemblies, 11 the decorated SS rods are arranged at the outermost to ease the peaks.…”

Section: Modeling Of the Scwrsfmentioning

confidence: 99%

“…From the perspective of neutron physics, the energy spectrum of the SCWR is harder than that of the current light water reactor (LWR) due to the smaller coolant flow. An SCWR can be designed with a thermal 10 or fast spectrum, 11,12 which may enable core breeding and the management of actinide nuclides. In addition, it can be designed with a mixed spectrum with both advantages, which must fully consider the change of the moderating effect caused by the change of water density.…”

Section: Introductionmentioning

confidence: 99%

“…In the SuperFR concept design, the core with a complicated two‐pass coolant flow scheme (two‐pass core, Figure 2, left) 11 was designed to obtain several advantages, such as a uniform vertical coolant density distribution and flattened radial power distribution. However, there are also drawbacks, including that the complicated flow scheme requires complicated in‐core structures to guide the flow, the need for many penetrations and heat seals, and sudden change of flow directions.…”

Section: Introductionmentioning

confidence: 99%

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Preliminary study on physical characteristics of single‐pass super‐critical water‐cooled reactor core

et al. 2020

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Summary The super‐critical water‐cooled reactor (SCWR) is one of six types of Gen‐IV reactors. Based on the current mature pressurized water reactor technology, it has several advantages, including high conversion ratio, high breeding of nuclear fuel, high thermal efficiency, and a simplified system. However, due to the combination of water coolant and fast neutron spectrum, there is a need to address safety problems caused by the positive void coefficient. The purpose of this paper is to give a study on physical characteristics for the reactor core. Herein, the core modeling of an SCWR with a single‐pass flow is that seed assemblies and blanket assemblies are arranged in a tornado manner, in which MCNP and SERPENT are used for critical calculation. The assembly design is discussed from the aspects of the thickness of the solid moderator layer and cladding material. Based on the optimized assembly design, UO2, PuO2‐ThO2, and PuO2‐UO2 are selected for the sensitivity analysis of fuel composition. In addition, sensitivity analysis for axial coolant density distribution, water‐to‐fuel volume ratio, reflector thickness and fuel arrangement are carried out. Several fundamental system characteristics are discussed in this paper, including keff, void coefficient, Doppler coefficient, neutron spectrum, power distribution, one‐cycle burnup and conversion ratio. The results help in understanding the design of the SCWR better and provide fundamental research data for further study.

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Section: Modeling Of the Scwrsfmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Preliminary study on physical characteristics of single‐pass super‐critical water‐cooled reactor core

et al. 2020

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“…Experimental study of thermal hydraulics, materials and water chemistry as well as the design study of fast reactor version of SCWR were conducted in collaboration with the researchers of the universities and the research institutes in Japan with the competitive funding from our ministry, MEXT (Ministry of Education, Culture, Sports, Science and Technology) between 2005 and 2014. The experimental results and the results of SCWR design studies after the first volume are summarized in the second volume in 2014 (Oka 2014). The author retired from the University of Tokyo in 2010 and worked at Waseda university between 2010 and 2014.…”

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confidence: 99%

Review of SCWR research in Japan

Oka

2023

Front. Nucl. Eng.

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SCWR (supercritical water cooled reactor) is one of the Generation IV reactors. This review summarizes the results of SCWR design concept development through numerical simulations carried out by the author-led team at the University of Tokyo and Waseda University from 1989 to 2014. They are core design, subchannel analysis, statistical thermal design, fuel rod design, development of fuel integrity criteria, plant system and heat balance, plant dynamics analysis, plant control, startup system, stability analysis, safety principle, safety criteria, safety analysis, transient subchannel analysis and fast reactor SCWR. A brief summary of experimental results on thermal hydraulics, materials and water chemistry follows. Discussion includes SCPR study by Japanese BWR manufacturers, comments on the 2005 INEEL SCWR report, misconceptions about SCWR and commercialization challenges. The SCWR is an innovation in light water reactors based on supercritical coal-fired power plant technology that has been in use worldwide for over half a century. This review covers most of the SCWR design and analysis. For researchers, it is a good subject to understand the design and analysis of light water reactors.

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Holistic Approach to Safety and Operational Stability: Analyzing VVER-1200 Reactor Dynamics in SGTR and AC Power Loss

Rah,

Joarder,

Hashan

et al. 2024

Preprint

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VVER-1200 (Water-Water Energetic Reactor) represents a significant advancement in nuclear power generation, emphasizing the continuous analysis and enhancement of safety systems for reliable operation. The proposed study focuses on simulating combined scenarios involving steam generator tube rupture (SGTR) and AC power loss using core algorithms and models within personal computer transient analyzer (PCTRAN). Reactor kinetic equations, thermal-hydraulic balance, and safety system models are discussed to elucidate their role in simulating SGTR and AC power loss. Safety criteria, boundaries and initial conditions are outlined to provide a comprehensive understanding of the simulation framework. The analysis delves into dynamic behavior of VVER-1200, placing emphasis on thermal-hydraulic implications, essential reactor parameters, and radiation monitoring to facilitate impact evaluation. Continuous monitoring and maintenance of safety systems are underscored to ensure stable core cooling, particularly during proposed transient conditions. Through meticulous analysis and comparison with established benchmarks, this study contributes to bolstering the safety and reliability of VVER-1200 reactors by identifying vulnerabilities, assessing mitigation strategies, and refining emergency response protocols. Practical implications of this study offer a crucial understanding of reactor behavior, safety system performance, and emergency response strategies, thereby improving safety, optimizing operational practices, and reducing risks in nuclear reactor accidents.

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Reactor Design and Safety

Cited by 3 publications

References 71 publications

Preliminary study on physical characteristics of single‐pass super‐critical water‐cooled reactor core

Preliminary study on physical characteristics of single‐pass super‐critical water‐cooled reactor core

Review of SCWR research in Japan

Holistic Approach to Safety and Operational Stability: Analyzing VVER-1200 Reactor Dynamics in SGTR and AC Power Loss

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