A Three Dimensional investigation of Xenon and temperature transients
Description
The Paper describes the development of a Three Dimensional Xenon and temperature feedback transient code for Advanced Gas Cooled Reactors. This has been based on a standard UK Three Dimensional Fuel Management code which has all the necessary irradiation and flux restart options so that transients can be followed at any point in the reactors' life history. It incorporates both a conventional eigenvalue calculation and some rather novel flux solution techniques e.g. to shape the radial power distribution by means of the stainless steel 'grey' rods to yield a desired macroscopic shape. Detailed solution of the Xenon and Iodine number densities is performed by a Runge-Kutta integration routine while the fuel and moderator temperatures including re-entrant flow are modelled by newly developed procedures which are fast yet accurate. Results for several transients will be presented in the paper together with comparisons with simpler one dimensional models
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- LaGrange Park, IL (USA)
- ISBN
- 0-919784-02-X
- Imprint Title
- Proceedings of the international conference on numerical methods in nuclear engineering. Volume 1
- Journal Page Range
- p. 580-602.
Conference
- Title
- International conference on numerical methods in nuclear engineering.
- Dates
- 6-9 Sep 1983.
- Place
- Montreal (Canada).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17051803
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGR TYPE REACTORS; COMPUTER CODES; EIGENVALUES; FLOW MODELS; IRRADIATION; MODERATORS; NUCLEAR FUELS; ONE-DIMENSIONAL CALCULATIONS; POWER DISTRIBUTION; REACTOR CORES; RUNGE-KUTTA METHOD; SPATIAL DISTRIBUTION; STAINLESS STEELS; TEMPERATURE DISTRIBUTION; TRANSIENTS; XENON
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; DISTRIBUTION; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HIGH ALLOY STEELS; INTERPOLATION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MATHEMATICAL MODELS; NONMETALS; NUMERICAL SOLUTION; RARE GASES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; STEELS