Published September 1999
| Version v1
Book
Design calculations of the thermal-spectrum accelerator-driven system for LWR waste destruction
Creators
- 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)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 53059303
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S43: PARTICLE ACCELERATORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCELERATORS; BURNUP; DESIGN; GRAPHITE; KINETICS; MOLTEN SALT REACTORS; NUCLEAR PHYSICS; RADIATION PROTECTION; RADIOACTIVE WASTES; SALTS; SPECTRA; TEMPERATURE COEFFICIENT; WASTE PROCESSING
- Descriptors DEC
- CARBON; ELEMENTS; MANAGEMENT; MATERIALS; MINERALS; NONMETALS; PHYSICS; PROCESSING; RADIOACTIVE MATERIALS; REACTIVITY COEFFICIENTS; REACTORS; WASTE MANAGEMENT; WASTES
Optional Information
- Notes
- 5 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)