Design and development of the AHWR—the Indian thorium fuelled innovative nuclear reactor
| Autor: | Anil Kakodkar, R.K. Sinha |
|---|---|
| Rok vydání: | 2006 |
| Předmět: |
Nuclear and High Energy Physics
Engineering Waste management business.industry Mechanical Engineering Nuclear engineering Nuclear reactor Nuclear power Natural uranium Void coefficient law.invention Thorium fuel cycle Advanced heavy-water reactor Nuclear Energy and Engineering Nuclear reactor core law General Materials Science Safety Risk Reliability and Quality business Waste Management and Disposal Liquid fluoride thorium reactor |
| Zdroj: | Nuclear Engineering and Design. 236:683-700 |
| ISSN: | 0029-5493 |
| DOI: | 10.1016/j.nucengdes.2005.09.026 |
| Popis: | India has chalked out a nuclear power program based on its domestic resource position of uranium and thorium. The first stage started with setting up the Pressurized Heavy Water Reactors (PHWR) based on natural uranium and pressure tube technology. In the second phase, the fissile material base will be multiplied in Fast Breeder Reactors using the plutonium obtained from the PHWRs. Considering the large thorium reserves in India, the future nuclear power program will be based on thorium–233U fuel cycle. However, there is a need for the timely development of thorium-based technologies for the entire fuel cycle. The Advanced Heavy Water Reactor (AHWR) has been designed to fulfill this need. The AHWR is a 300 MWe, vertical, pressure tube type, heavy water moderated, boiling light water cooled natural circulation reactor. The fuel consists of (Th–Pu)O2 and (Th–233U)O2 pins. The fuel cluster is designed to generate maximum energy out of 233U, which is bred in situ from thorium and has a slightly negative void coefficient of reactivity. For the AHWR, the well-proven pressure tube technology has been adopted and many passive safety features, consistent with the international trend, have been incorporated. A distinguishing feature which makes this reactor unique, from other conventional nuclear power reactors is the fact that it is designed to remove core heat by natural circulation, under normal operating conditions, eliminating the need of pumps. In addition to this passive feature, several innovative passive safety systems have been incorporated in the design, for decay heat removal under shut down condition and mitigation of postulated accident conditions. The design of the reactor has progressively undergone modifications and improvements based on the feedbacks from the analytical and the experimental R&D. This paper gives the details of the current design of the AHWR. |
| Databáze: | OpenAIRE |
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