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Graphite thermal decontamination with reducing gases

A graphite and gas technology, applied in radioactive purification, reactors, nuclear engineering, etc., can solve problems such as reducing to 5% (5%, unable to achieve weight percentage, etc.)

Active Publication Date: 2014-11-05
ELECTRICITE DE FRANCE
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

In either case, reducing the weight percent vaporization of bulk graphite to less than five (5) percent by weight while volatilizing more than ninety (90) percent of the carbon-14 cannot be achieved by these conventional methods. Target

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  • Graphite thermal decontamination with reducing gases
  • Graphite thermal decontamination with reducing gases
  • Graphite thermal decontamination with reducing gases

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Embodiment Construction

[0025] Exemplary embodiments of the present invention provide systems and methods for processing radioactive graphite contaminated with tritium, carbon-14 and chlorine-36, and other radionuclides produced during the operation of a nuclear reactor or other nuclear process. The systems and methods include a roaster operating at a temperature range of 800°C to 2000°C with inert, optional oxidizing and reducing gases. The combination of temperature and gas makes it possible to remove 90 percent of the carbon-14 in the graphite while vaporizing less than 5 percent of the bulk graphite.

[0026] figure 1 A block diagram of a system 100 for processing radioactive graphite according to an exemplary embodiment of the invention is depicted. about figure 1 , the material handling element 110 contains graphite to be processed in the system 100 . Typically, graphite is used as a moderator in nuclear reactor cores. Other sources of graphite include, but are not limited to, fuel element ...

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Abstract

Providing a roaster that operates at temperatures in the range of 800° Celsius to 2000° Celsius with inert, optional oxidizing and reducing gases to treat graphite contaminated with radionuclides including tritium, carbon-14, and chlorine-36. The combination of temperatures and gases allow for the removal of most to substantially all the carbon-14 within the graphite while substantially limiting gasifying the bulk graphite.

Description

technical field [0001] The present invention generally relates to graphite purification methods employing heat treatment with purge gases including reducing gases to remove tritium, carbon-14 and chlorine-36. Background technique [0002] Graphite, mainly composed of carbon, is used as a moderator in many nuclear reactor designs, such as the UK's MAGNOX and Advanced Gas-Cooled Reactors (AGR) and the Russian High Power Tube Reactor (RBMK) design. During construction, the reactor's moderator is usually installed as an interlocking structure of graphite blocks. At the end of the reactor life, the graphite moderator typically weighs around 2000 tonnes and requires safe disposal as a form of radioactive waste. Graphite is a relatively stable chemical form of carbon that can be processed directly without processing in a variety of ways. However, after neutron irradiation, graphite will contain Wigner energy. A possible means of releasing this energy needs to be included in any...

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Application Information

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IPC IPC(8): G21F9/14G21C1/00G21F9/00
CPCG21F9/32G21F9/14
Inventor J·布雷德利·马松托马斯·布朗萨哈·托拉布扎代赫乔纳森·奥兰德
Owner ELECTRICITE DE FRANCE