Published September 1999 | Version v1
Book

Design calculations of the thermal-spectrum accelerator-driven system for LWR waste destruction

  • 1. Skoda JS s.r.o.. Orlilc 266, 316 06 Plzen (Czech Republic)

Description

A number of nuclear physics design issues concerning Accelerator Driven Molten-Salt Reactor based on the so called ATW concept proposed by Los Alamos are discussed. General description of concept using internal moderation with graphite block is presented. Burn-up, salt processing and safety criteria (reactivity temperature coefficients and kinetics parameters) are presented for different spectra (graphite to salt ratio) and an optimal variant of the blanket with non-positive temperature reactivity coefficient is provided and results are discussed

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
Jackson Hole, Wyoming (United States)
Imprint Pagination
7 p.

Conference

Title
International Conference on Future Nuclear Systems - Nuclear Technology - Bridging the Millennia
Acronym
Global'99
Dates
29 Aug - 3 Sep 1999
Place
Las Vegas, NV (United States)

Optional Information

Notes
5 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)