Coupling of Nod1D and HOTCHANNEL: static case
Creators
- 1. IPN-ESFM, 07738 Mexico D.F. (Mexico)
- 2. IIE-Gcia. de Energia Nuclear, Cuernavaca, Morelos (Mexico)
Description
In this work the joining of the programs Nod1D and HOTCHANNEL, developed in the National Polytechnic Institute (IPN) and in the Electrical Research Institute (IIE) respectively is described. The first one allows to study the neutronic of a nuclear reactor and the second one allows to carry out the analysis of hot channel of a Boiling Water Reactor (BWR). Nod1 D is a program that it solves by nodal methods type finite element those diffusion equations in multigroup, and it is the static part of Nod Kin that it solves the diffusion equation in their time dependent part. For another side HOTCHANNEL is based on a mathematical model constituted by four conservation equations (two of mass conservation, one of motion quantity and one of energy), which are solved applying one discretization in implicit finite differences. Both programs have been verified in independent form using diverse test problems. In this work the modifications that were necessary to carry out to both for obtaining a coupled program that it provides the axial distribution of the neutron flux, the power, the burnup and the void fraction, among others parameters as much as neutronic as thermal hydraulics are described. Those are also mentioned limitations, advantages and disadvantages of the final product to which has been designated Nod1 D-HotChn. Diverse results for the Cycle 1 of the Laguna Verde Unit 1 reactor of the Nucleo electric central comparing them with those obtained directly with the CoreMasterPresto code are provided. (Author)
Availability note (English)
Available from INIS in electronic formFiles
36115688.pdf
Files
(258.4 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:5ee8b86d1819301174648f48ec3de323
|
258.4 kB | Preview Download |
Additional details
Additional titles
- Original title (Spanish)
- Acoplamiento de Nod1D y HOTCHANNEL: caso estatico
Publishing Information
- Imprint Pagination
- 16 p.
- Report number
- INIS-MX--1942
Conference
- Title
- 14. Annual Congress of the SNM; 21. Annual Meeting of the SMSR
- Original Conference Title
- Energia Nuclear y Seguridad Radiologica: Nuevos retos y perspectivas
- Dates
- 10-13 Sep 2003
- Place
- Guadalajara (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 36115688
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; C CODES; COMPUTER CODES; CROSS SECTIONS; DIFFUSION EQUATIONS; FINITE ELEMENT METHOD; FUEL ASSEMBLIES; FUEL CELLS; LAGUNA VERDE-1 REACTOR; MATHEMATICAL MODELS; MULTIGROUP THEORY; NEUTRON FLUX; NEUTRONS; THERMAL HYDRAULICS; VOID FRACTION
- Descriptors DEC
- BARYONS; BWR TYPE REACTORS; CALCULATION METHODS; COMPUTER CODES; DIFFERENTIAL EQUATIONS; DIRECT ENERGY CONVERTERS; ELECTROCHEMICAL CELLS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; EQUATIONS; FERMIONS; FLUID MECHANICS; HADRONS; HYDRAULICS; MATHEMATICAL SOLUTIONS; MECHANICS; NEUTRON TRANSPORT THEORY; NUCLEONS; NUMERICAL SOLUTION; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; RADIATION FLUX; REACTORS; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS