Published September 1, 2007 | Version v1
Miscellaneous

A Modular Radiant-Heat-Initiated Passive Decay-Heat-Removal System for Salt-Cooled Reactors

  • 1. Oak Ridge National Lab., Oak Ridge, TN (United States)

Description

The Advanced High-Temperature Reactor (AHTR), also called the liquid-salt-cooled very high temperature reactor, is a new reactor concept that combines four existing technologies to create a new reactor option: coated-particle graphite-matrix fuels (the same fuel as used in high-temperature gas-cooled reactors), a liquid-fluoride-salt coolant with a boiling point >1200 C, Brayton power cycles, and passive safety systems. A new passive decay-heat cooling system has been invented that is actuated by the increased temperature of the salt under accident conditions and uses radiant heat transfer from and through the salt to a heat exchanger. This safety system takes advantage of two physical properties of the system: (1) the transparency of the salt coolant and (2) the increase in the radiant heat transfer from the salt to a decay-heat exchanger, which is proportional to the temperature of the hot salt to the fourth power (T4) minus the temperature of the heat exchanger surface to the fourth power (T4). For a high-temperature reactor, small increases in coolant temperatures dramatically increase radiant heat transfer

Availability note (English)

Available from Oak Ridge National Laboratory (US)

Additional details

Publishing Information

Imprint Pagination
vp.

Conference

Title
Advanced Nuclear Fuel Cycles and Systems
Acronym
GLOBAL'07
Dates
9-13 Sep 2007
Place
Boise, ID (United States)

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
40013730
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ACCIDENTS; BOILING POINTS; COOLANTS; COOLING SYSTEMS; HEAT EXCHANGERS; NUCLEAR FUELS; PHYSICAL PROPERTIES; RADIANT HEAT TRANSFER; SAFETY
Descriptors DEC
ENERGY SOURCES; ENERGY SYSTEMS; ENERGY TRANSFER; FUELS; HEAT TRANSFER; MATERIALS; PHYSICAL PROPERTIES; REACTOR MATERIALS; THERMODYNAMIC PROPERTIES; TRANSITION TEMPERATURE

Optional Information

Contract/Grant/Project number
AF3620800; NEAF265; AC05-00OR22725
Funding organization
NE USDOE - Office of Nuclear Energy (United States)
Secondary number(s)
ORNL/PTS--7206