PRISM (Power Reactor Inherently Safe Module) design concept enhances waste management
PRISM, a modular advanced liquid metal reactor (ALMR), has been designed conceptually by GE under the US Department of Energy sponsorship. The concept design and analyses have been primarily focused on passive safety and improved construction and operating costs. Significantly, the unique design of multiple modules and features of PRISM enhance waste management over conventional reactor systems. This paper provides an overview of PRISM of these enhancements. Inherent to the ALMR's, the sodium coolant precludes crud buildup on reactor surfaces and in components and waste for disposal. Preliminary evaluations indicate this fundamental feature results in factors of 2-4 less waste volume and 2-3 orders of magnitude less curies per megawatt-electric for ultimate disposal. For example, the tap designed for sodium cleanup is expected to be exchanged only once every thirty years. Also, inherent to ALMR's, burning waste actinides and selected fission products to preclude their accumulation and burial is very attractive. The hard neutron spectrum of ALMR burns the actinides efficiently and is not poisoned by the actinides and fission products. The modular design of PRISM components (and the fuel cycle equipment) permit replacement without expensive and potentially hazardous volume reduction. For example, the functional components of the reference electromagnetic pump and IHK can be removed intact for waste disposal. Although development of the reference metal fuel is not completed, it is estimated that (low-level) waste from recycle of the fuel will result in significantly less volume than would be generated by aqueous recycle of oxide fuel. 6 refs., 10 figs.
- Research Organization:
- General Electric Co., San Jose, CA (USA). Advanced Nuclear Technology
- DOE Contract Number:
- AC03-85NE37937
- OSTI ID:
- 6161920
- Report Number(s):
- CONF-890218-4; ON: DE89008047
- Resource Relation:
- Conference: 16. annual WATTec conference and exhibition, Knoxville, TN, USA, 14 Feb 1989; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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LMFBR TYPE REACTORS
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RADIOACTIVE WASTE MANAGEMENT
AFTER-HEAT REMOVAL
COST
ECONOMICS
POWER DISTRIBUTION
REACTIVITY
REACTOR COMPONENTS
REACTOR SAFETY
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ELEMENTS
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ISOTOPES
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OXIDATION
RADIOACTIVE MATERIALS
REACTORS
REMOVAL
SAFETY
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