Published 2007 | Version v1
Miscellaneous Metadata-only

COTHA-2tp: a code for two-phase flow analysis of PWR cores using the homogeneous model

Creators

  • 1. Centro Tecnico Aeroespacial (CTA-IEAv), Sao Jose dos Campos, SP (Brazil). Inst. de Estudos Avancados

Description

This work presents a development of a code to perform thermo-hydraulic analysis in PWR nuclear reactor cores. This code is based on the COTHA-2 code, increased of the homogeneous model two-phase flow analysis capability. This study is restricted to one-dimensional geometry and steady state calculations. The results obtained with the developed code show a good agreement with results generated with the COBRA-EN code (author)

Part of:
Proceedings of the INAC 2007 International nuclear atlantic conference. Nuclear energy and energetic challenges for 21st. century. 15. Brazilian national meeting on reactor physics and thermal hydraulics; 8. Brazilian national meeting on nuclear applications

Additional details

Publishing Information

ISBN
978-85-99141-02-1
Imprint Title
Proceedings of the INAC 2007 International nuclear atlantic conference. Nuclear energy and energetic challenges for 21st. century. 15. Brazilian national meeting on reactor physics and thermal hydraulics; 8. Brazilian national meeting on nuclear applications
Imprint Pagination
[vp.]
Journal Page Range
[6 p.]

Conference

Title
INAC 2007 International nuclear atlantic conference. Nuclear energy and energetic challenges for 21st. century. 15. Brazilian national meeting on reactor physics and thermal hydraulics; 8. Brazilian national meeting on nuclear applications
Dates
30 Sep - 5 Oct 2007
Place
Santos, SP (Brazil)

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
39084785
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
C CODES; ENERGY CONSERVATION; EXPERIMENTAL DATA; ONE-DIMENSIONAL CALCULATIONS; PWR TYPE REACTORS; REACTOR CHANNELS; REACTOR CORES; TWO-PHASE FLOW; VOID FRACTION
Descriptors DEC
COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; FLUID FLOW; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
6 refs., 3 figs., 1 tab. Code: R02_781.pdf