Next Generation Nuclear Plant: High-Level Functions and Requirements

2004 ◽  
Author(s):  
John M. Ryskamp ◽  
Edwin A. Harvego ◽  
Soli T. Khericha ◽  
Edward J. Gorski ◽  
George A. Beitel ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Nuclear Plant ◽  
Department Of Energy ◽  
Next Generation ◽  
Very High Temperature Reactor ◽  
Environmental Laboratory ◽  
High Temperature Reactor ◽  
High Level ◽  
Very High ◽  
Selection Of

The Idaho National Engineering and Environmental Laboratory (INEEL) prepared a functions and requirements (F&R) document for the Next Generation Nuclear Plant (NGNP) Project [1] The highest-level functions and requirements for the NGNP Project design are identified in the F&R document, which establishes performance definitions to be achieved by the NGNP. The requirements for the NGNP are based on the Generation IV roadmap [2] goals. Based on these requirements, NGNP designs will be developed by commercial vendor(s). Of the six most promising Generation IV nuclear energy systems, the Very High Temperature Reactor (VHTR) is the nearest-term reactor concept that also has the capability to efficiently produce hydrogen. The U.S. Department of Energy (DOE) has selected the VHTR as the concept to demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. This paper reviews the NGNP Project and the selection of the VHTR, then presents the NGNP functions and requirements.

Project Deep-Burn: Development of Transuranic Fuel for High-Temperature Helium-Cooled Reactors

2008 ◽  
Author(s):  
Robert M. Versluis ◽  
Francesco Venneri ◽  
David Petti ◽  
Lance Snead ◽  
Donald McEachern
Keyword(s):  
High Temperature ◽  
Nuclear Plant ◽  
Next Generation ◽  
Very High Temperature Reactor ◽  
High Temperature Reactor ◽  
Very High ◽  
The U.S

The helium-cooled, graphite-moderated Very High Temperature Reactor (VHTR) has become the centerpiece of the U.S. Department of Energy’s (DOE) Next Generation Nuclear Plant (NGNP) program. The NGNP program aims to construct a VHTR prototype, with the participation of industry, by the year 2021.

Effects of Bypass Flow on the LOFA Transient Computations in a VHTR

2013 ◽  
Author(s):  
Yu-Hsin Tung ◽  
Richard W. Johnson ◽  
Yuh-Ming Ferng ◽  
Ching-Chang Chieng
Keyword(s):  
Nuclear Power ◽  
Natural Circulation ◽  
Cfd Model ◽  
Bypass Flow ◽  
The Core ◽  
Active Core ◽  
Very High Temperature Reactor ◽  
High Temperature Reactor ◽  
Very High ◽  
Helium Coolant

The prismatic gas-cooled very high temperature reactor (VHTR) is one possible option for the generation IV nuclear power plant. The prismatic VHTR basically involves stacks of hexagonal graphite blocks that are drilled to accept cylindrical fuel compacts and provide coolant channels for the helium coolant. Between the hexagonal blocks, there are gaps, which allow the coolant flow to bypass the coolant channels. The gaps are not intentionally designed to occur in the core, but are present because of tolerances in machining the blocks, imperfect installation and expansion and shrinkage from heating and irradiation. Based on previous studies of a loss of flow accident (LOFA), the cooling provided by flow in the bypass gaps has a significant effect on the nature and strength of the attendant natural circulation. One of the mechanisms that occurs after a LOFA for the transport of heat out of the core is by the natural convection of the coolant. It is of interest to know if there are problems for the core associated with the natural circulation and what is the role played by the bypass flow in such an event. The distribution of heat generation and the separation of the partial columns included in the CFD model of the heated core have a strong effect on the natural circulation. In the present paper, a 1/12 symmetric section of the active core is considered for the CFD model. Two regions of the 1/12 section are employed to perform the LOFA transient calculations. Several scenarios are investigated including with and without the bypass gap in the model. The present study also reports the effects of bypass flow on the natural circulation with time for these cases.

scholarly journals Characterization of 2D-C/C Composite for Application of Very High Temperature Reactor(M & M 2009 Conference)

2010 ◽  
Vol 76 (764) ◽  
pp. 383-385 ◽  
Author(s):  
Taiju SHIBATA ◽  
Junya SUMITA ◽  
Taiyo MAKITA ◽  
Takashi TAKAGI ◽  
Eiji KUNIMOTO ◽  
...  
Keyword(s):  
High Temperature ◽  
Special Issue ◽  
Very High Temperature Reactor ◽  
High Temperature Reactor ◽  
Very High

Performance Comparison of VHTR Plants With Direct and Indirect Energy Conversion Cycles

2008 ◽  
Author(s):  
Mohamed S. El-Genk ◽  
Jean-Michel Tournier
Keyword(s):  
Pressure Ratio ◽  
Thermal Power ◽  
Performance Comparison ◽  
Working Fluid ◽  
Helium 4 ◽  
Very High Temperature Reactor ◽  
Exit Temperature ◽  
High Temperature Reactor ◽  
Very High ◽  
Reactor Pressure

This paper compared the performance of very high temperature reactor (VHTR) plants with direct and indirect closed Brayton Cycles (CBCs) and investigated the effect of the molecular weight of the CBC working fluid on the number of stages in and the size of the single shaft turbomachines. The CBC working fluids considered are helium (4 g/mole) and He-Xe and He-N2 binary mixtures (15 g/mole). Also investigated are the effects of using LPC and HPC with inter-cooling, cooling the reactor pressure vessel with He bled off at the exit of the compressor, and changing the reactor exit temperature from 700°C to 950°C on the plant thermal efficiency, CBC pressure ratio and the number of stages in and size of the turbo-machines. Analyses are performed for reactor thermal power of 600 MW, shaft rotation speed of 3000 rpm, and IHX temperature pinch of 50 °C.

Regulatory Viewpoint on Innovative VHTR Development in Korea

2008 ◽  
Author(s):  
Hun-Joo Lee ◽  
Sang-Kyu Ahn ◽  
Kju-Myeng Oh ◽  
Chang-Ju Lee
Keyword(s):  
Research Effort ◽  
Policy Statement ◽  
Light Water Reactors ◽  
Event Frequency ◽  
Very High Temperature Reactor ◽  
Regulatory Approach ◽  
High Temperature Reactor ◽  
Water Reactors ◽  
Gen Iv ◽  
Very High

This paper addresses that major changes in the safety approach, for instance the increased use of Probabilistic Risk Assessment (PRA), have been made. All commercial reactors in operation today belong to the Generations II and III. Generation IV International Forum (GIF) has launched several programs aimed at developing the next generation of nuclear energy systems. Part of the research effort is focused on new reactor concepts, such as the Very High Temperature Reactor (VHTR), currently developing in Korea. In parallel to the design process of VHTR currently underway, regulatory approach is moving forward to define new licensing rules. So, Korea Institute of Nuclear Safety (KINS) is defining, as a goal to risk-inform, the regulation and developing the regulatory framework and licensing process more efficient, predictable, and stable. However, the licensing of NPPs has focused until now on Light Water Reactors (LWRs) and has not incorporated systematically insights and benefits from PRA. In the meantime, USNRC and IAEA have recently drafted a risk-informed regulation and technology-neutral framework (TNF) for new plant licensing along with the innovative Gen-IV system design. KINS also expects that advanced NPPs will show enhanced margins of safety, and that advanced reactor designs will comply with the national safety goal policy statement. In order to meet these expectations, PRA tools are currently being considered by KINS; among them are frequency-consequence (F-C) curves, which plot the frequency of having Consequence. This paper discusses the role and the usefulness of such curves in risk-informing the licensing process in Korea, and shows that the use of F-C curve allows the implementation of both structural and rational Defence-In-Depth (DID). This paper focuses on F-C curves as means to assess the licensing basis events (LBEs) from the regulatory viewpoint on the innovative small and medium reactor (SMR) sized VHTR deployment in Korea. The principle underlying the F-C curve is that event frequency and dose are inversely related, i.e., the higher the dose consequences, the lower is the allowed event frequency.

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