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Monday, August 10, 2020 | History

2 edition of Core design study for an advanced HTGR found in the catalog.

Core design study for an advanced HTGR

A. M. Baxter

Core design study for an advanced HTGR

by A. M. Baxter

  • 269 Want to read
  • 12 Currently reading

Published by Dept. of Energy, for sale by the National Technical Information Service in Washington, Springfield, Va .
Written in English

    Subjects:
  • Gas cooled reactors

  • Edition Notes

    Statementby A. M. Baxter and P. A. Iyer
    SeriesGA-A ; 14571
    ContributionsIyer, P. A. joint author, United States. Dept. of Energy. San Francisco Operations Office, General Atomic Company
    The Physical Object
    Paginationviii, 78 p. :
    Number of Pages78
    ID Numbers
    Open LibraryOL14879488M

     Future-proof your Design.  Architect Registers for Easy Implementation.  Architect for Future Growth.  High-speed Design.  Use One-hot States. design and licensing of an advanced HTGR and the associated advanced technologies to transport the high temperature process heat. The basis for the HTGR technology embodied in the NGNP was first developed over 40 years ago in the UK, the US and Germany. Most of the previous work has focused on the generation of Size: 5MB.

      The book also details current and potential innovations in plant design, examining challenges likely to be faced by the nuclear power industry in meeting future energy demands. investigating topics such as reactor systems, cost-effective fuel management, environmental issues, and the design of future : $ About the Author   Kishore Mishra started his career as a design engineer working on Ethernet chip design almost 20 years back at Allied Telesyn, International. Since then he has worked on chip design and architecture in multinational companies such as Texas Instruments and Intel Corporation.

    (shelved 1 time as advanced-3rd-grade-reader) avg rating — 6, ratings — published The Jeremiah Institute is pleased to announce the addition of a new biblical study series: Core Study Series. As the title suggests this series will present the core truths about a Bible subject. We all have numerous time constraints placed on us in our busy day-to-day lives.


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Core design study for an advanced HTGR by A. M. Baxter Download PDF EPUB FB2

Core design study for an advanced HTGR. [A M Baxter; P A Iyer; United States. Department of Energy. based on reference standards.

However, formatting rules can vary widely between applications and fields of interest or study. The specific requirements or preferences of your reviewing publisher, classroom teacher, institution or organization.

The high-temperature gas-cooled reactor (HTGR) is similar in concept to the AGR. It uses uranium fuel, a graphite moderator and a gas as a coolant.

In this case, however, the gas is helium. Several attempts have been made to build reactors of this type, but none has so far entered commercial service. Early development work was carried out in. The very-high-temperature reactor (VHTR), or high-temperature gas-cooled reactor (HTGR), is a Generation IV reactor concept that uses a graphite-moderated nuclear reactor with a once-through uranium fuel cycle.

The VHTR is a type of high-temperature reactor (HTR) that can conceptually have an outlet temperature of °C. The reactor core can be either a. @article{osti_, title = {HTGR risk assessment study}, author = {Joksimovic, V and Houghton, W J and Emon, D E}, abstractNote = {The Accident Initiation and Progression Analysis (AIPA) Study being performed for the high-temperature gas-cooled reactor (HTGR) utilizes methods of probabilistic risk assessment similar to those used in the Reactor Safety Study.

Optimizing the performance and design of a prismatic core HTGR or VHTR requires a full core thermal-hydraulics analysis. Owing to the complexity and massive core structure, such analysis requires extensive and massively parallelized computation capabilities and a relatively long time (weeks to months) to complete.

This paper describes a preliminary analysis of a large HTGR [ MW (t)] core using a prismatic fuel with coolant gas core outlet temperatures of C ( F). This study provides core design considerations in the areas of radial fuel zoning, power distribution, fuel performance, fuel temperatures, and fission product release for a large Author: R.

Rao, A. Baxter. Since Japan has launched a study of PuO 2 –YSZ (yttria-stabilized zirconia) fuel and core design with a burnup limit of GWd/t with the aim to validate clean burning of plutonium in HTGR (Goto et al., ). Spent fuel may be directly disposed or by: 3.

"Development of Security and Safety Fuel for Pu-Burner HTGR: Part 2 — Design Study of Fuel and Reactor Core." Proceedings of the 25th International Conference on Nuclear Engineering.

Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues. Shanghai, : Minoru Goto, Shohei Ueta, Jun Aihara, Yoshitomo Inaba, Yuji Fukaya, Yukio Tachibana, Koji Okamoto. IN-CORE STRUCTURAL MATERIALS AND COMPONENTS Hexagonal block fuel elements for the prismatic HTGR design In-core graphitic materials In-core ceramic and ceramic composite materials 7.

TRISO-COATED PARTICLE FUEL IRRADIATIONS Past irradiation performance State of the art in TRISO-coated particle fuel irradiations File Size: 3MB. The system codes non-specific for HTGR such as RELAP5 has been utilized for HTGR thermal hydraulic analysis even helium gas property is not based on KTA Core design for a small HTGR.

Author(s) Ribeiro, Arnaldo Aloisio Telles; Lanning David D. Downloadpdf (Mb) Other Contributors. Massachusetts Institute of Technology. Department of Nuclear Engineering.

Metadata Show full item record. by: 1. Core design Quality of ride • Elevator shaft area should be at least 20% greater than the car platform area • Guide rails with fixing point s at a maximum of m are required to provide a rigid running surface for the car guides.

• Guide-rail alignment must allow for vertical movement. The section of core thermal-hydraulic design explains the outline of the coolant flow allocation procedure and the evaluation methods of temperature distributions in a fuel subassembly.

The author of Sect. is Hiroo Osada. Section describes design of high temperature gas-cooled reactor (HTGR).Author: Hiroo Osada, Kiyonobu Yamashita.

3 FOREWORD Although the number of new reactors under construction or commissioning worldwide are very few, the field of advanced reactor and fuel design is thriving.

The data presented refer to both the and the KW core. The WIMS k eff values, versus moderation ratio from 7 to 11, are shown in figure 4. The. Results of the Phase 1 tests led to improvements in the post/seat design. Phase Table 1HTGR core seismic test program No. Task Description Status Pendulum collision test (1/5, 1/2, and 1/1 scale) Coefficient of restitution - model scaling laws Completed Multiblock collision test (1/5, 1/2, and 1/1 Study collision behavior - correlation with.

This paper describes design of core components of HTTR and R&D on nuclear graphite for HTGR. JAEA established the graphite structural design code and inspection standard of graphite to construct the HTTR.

JAEA developed an in-service inspection method and a draft graphite structural design code for future HTGR on the basis of the HTTR technologies.

Core Design. The reactor core is a low power density design that consists of an annular array of hexagonal blocks of graphite fuel elements surrounded by a reflector of unfueled graphite blocks. The design is intended to provide efficient heat transfer to the exterior in order to limit the temperature rise of the fuel in the event of a LOCA.

Core Analysis: A Best Practice Guide is a practical guide to the design of core analysis programs. Written to address the need for an updated set of recommended practices covering special core analysis and geomechanics tests, the book also provides unique insights into data quality control diagnosis and data utilization in reservoir by:   The amount of structure in the advanced cores is minimized by utilizing thin (3 mm) fuel assembly duct walls and increasing Table 4Summary of core design parameters for GCFR scoping study Core Primary system pressure (MPa) Peak linear rating (kW/m) Number of fuel assemblies Core height (mm) Core diameter (cylinder) (mm) Core AP (kPa) Fuel cycle.

R. A. Rucker, “ MW(t) MHTGR Core Nuclear Design,” DOE-HTGR, General Atomics, September Google Scholar 7. F.A. Silady, W.A. Simon, “Innovative Safety Features of the Modular HTGR,” GA-A, General Atomics, April Google ScholarAuthor: Hangbok Choi, Robert Schleicher, Myunghee Choi.In the HTGR design, generally, boron is loaded into the core as a burnable poison to suppress excess reactivity.

In this study, lithium is loaded into the HTGR core instead of boron and is used as a burnable poison aiming to produce thermal energy and tritium simultaneously.That's why the world needs hardware wizards, and the best gauge of hardware wizardry around today is the A+ certification.

If you're out to earn your A+ ticket, David Groth's A+: Core Module Study Guide is an excellent resource. At first glance, the book does have a few drawbacks/5(6).