The Advanced High-Temperature Reactor: High-Temperature Fuel, Molten Salt Coolant, and Liquid-Metal-Reactor Plant

نویسندگان

  • Charles Forsberg
  • CHARLES FORSBERG
چکیده

The Advanced High-Temperature Reactor is a new reactor concept that combines four existing technologies in a new way: (1) coated-particle graphite-matrix nuclear fuels (traditionally used for helium-cooled reactors), (2) Brayton power cycles, (3) passive safety systems and plant designs from liquid-metal-cooled fast reactors, and (4) low-pressure molten-salt coolants with boiling points far above the maximum coolant temperature. The new combination of technologies enables the design of a large [2400to 4000-MW(t)] high-temperature reactor, with reactor-coolant exit temperatures between 700 and 1000EC (depending upon goals) and passive safety systems for economic production of electricity or hydrogen. The AHTR [2400-MW(t)] capital costs have been estimated to be 49 to 61% per kilowatt (electric) relative to modular gas-cooled [600-MW(t)] and modular liquid-metal-cooled reactors [1000-MW(t)], assuming a single AHTR and multiple modular units with the same total electrical output. Because of the similar fuel, core design, and power cycles, about 70% of the required research is shared with that for high-temperature gas-cooled reactors.

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

Pg. 1 of 1 Development Approaches for the Advanced High Temperature Reactor

The AHTR is a pool-type reactor with graphite matrix coated-particle fuel and a clean molten salt coolant [1]. Due to the very high thermal inertia provided by the pool configuration and molten-salt coolant of the AHTR, the thermal power of the AHTR can be substantially higher than an equivalent gas-cooled reactor, likely exceeding 2000 MW(t). The AHTR, with a molten-salt intermediate loop and ...

متن کامل

Passive Decay Heat Removal for the Advanced High Temperature Reactor

This report presents a design concept for a high-capacity decay-heat removal system for the molten-salt cooled Advanced High Temperature Reactor (AHTR) [1]. The design is closely derived from the General Electric S-PRISM reactor, which is a sodium pooltype reactor [2]. The AHTR is distinguished from the S-PRISM by its use of a hightemperature thermal blanket, shown in Fig.1, that allows the ves...

متن کامل

Modeling and Transient Analysis for the Modular Pebble-bed Advanced High Temperature

The Pebble Bed Advanced High Temperature Reactor (PB-AHTR) is a liquid-salt cooled reactor that uses conventional TRISO fuel. Due to the high thermal inertia of the liquid salt coolant, the PB-AHTR allows for a much higher power-density core than traditional gas-cooled high temperature reactors. High power density has a favorable economic impact. In 2007, the baseline design 2400MWth PB-AHTR wa...

متن کامل

Molten-salt Reactor Chemistry

This document summarizes the large program of chemical research and development which led to selection of fuel and coolant compositions for the Molten-Salt Reactor Experiment (MSRE) and for subsequent reactors of this type. Chemical behavior of the LiF-BeFrZrFrUF4 fuel mixture and behavior of fission products during power operation of MSRE are presented. A discussion of the chemical reactions w...

متن کامل

One-Dimensional Analysis of Thermal Stratification in AHTR and SFR Coolant Pools

Thermal stratification phenomena are very common in pool type reactor systems, such as the liquid-salt cooled Advanced High Temperature Reactor (AHTR) and liquid-metal cooled fast reactor systems. It is important to accurately predict the temperature and density distributions both for design optimization and accident analysis. Current reactor system analysis codes only provide lumped-volume bas...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

عنوان ژورنال:

دوره   شماره 

صفحات  -

تاریخ انتشار 2004