Uncertainty assessment for accelerator-driven systems.

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The concept of a subcritical system driven by an external source of neutrons provided by an accelerator ADS (Accelerator Driver System) has been recently revived and is becoming more popular in the world technical community with active programs in Europe, Russia, Japan, and the U.S. A general consensus has been reached in adopting for the subcritical component a fast spectrum liquid metal cooled configuration. Both a lead-bismuth eutectic, sodium and gas are being considered as a coolant; each has advantages and disadvantages. The major expected advantage is that subcriticality avoids reactivity induced transients. The potentially large subcriticality margin also should ... continued below

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11 p.

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Finck, P. J.; Gomes, I.; Micklich, B. & Palmiotti, G. June 10, 1999.

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Description

The concept of a subcritical system driven by an external source of neutrons provided by an accelerator ADS (Accelerator Driver System) has been recently revived and is becoming more popular in the world technical community with active programs in Europe, Russia, Japan, and the U.S. A general consensus has been reached in adopting for the subcritical component a fast spectrum liquid metal cooled configuration. Both a lead-bismuth eutectic, sodium and gas are being considered as a coolant; each has advantages and disadvantages. The major expected advantage is that subcriticality avoids reactivity induced transients. The potentially large subcriticality margin also should allow for the introduction of very significant quantities of waste products (minor Actinides and Fission Products) which negatively impact the safety characteristics of standard cores. In the U.S. these arguments are the basis for the development of the Accelerator Transmutation of Waste (ATW), which has significant potential in reducing nuclear waste levels. Up to now, neutronic calculations have not attached uncertainties on the values of the main nuclear integral parameters that characterize the system. Many of these parameters (e.g., degree of subcriticality) are crucial to demonstrate the validity and feasibility of this concept. In this paper we will consider uncertainties related to nuclear data only. The present knowledge of the cross sections of many isotopes that are not usually utilized in existing reactors (like Bi, Pb-207, Pb-208, and also Minor Actinides and Fission Products) suggests that uncertainties in the integral parameters will be significantly larger than for conventional reactor systems, and this raises concerns on the neutronic performance of those systems.

Physical Description

11 p.

Notes

INIS; OSTI as DE00011846

Medium: P; Size: 11 pages

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  • GLOBAL '99 International Conference on Future Nuclear Systems, Jackson Hole, WY (US), 08/30/1999--09/02/1999

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  • Report No.: ANL/RA/CP-99217
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 11846
  • Archival Resource Key: ark:/67531/metadc626459

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  • June 10, 1999

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • April 6, 2017, 7:47 p.m.

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Finck, P. J.; Gomes, I.; Micklich, B. & Palmiotti, G. Uncertainty assessment for accelerator-driven systems., article, June 10, 1999; Illinois. (digital.library.unt.edu/ark:/67531/metadc626459/: accessed July 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.