Published 1989
| Version v1
Miscellaneous
Comparison of pressure drop calculated by RELAP4/MOD5 code with results of DADINE experience
Creators
- 1. Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo, SP (Brazil)
Description
The objective of this paper is the evaluation of the DADINE pressure drop experimental data with RELAP4/MOD5 Code, in the context of theoretical/experimental comparison of the computational codes. The DADINE apparatus allows simulation of pressure drop experiments in the typical PWR cooling channels during the rewetting two-phase phenomena encountered in the LOCA accidents. The Code underestimated pressure drop due to inadequate evaluation of the two-phase gravity and friction loss terms. (author)
Availability note (English)
Available from the Library of Comissao Nacional de Energia Nuclear, RJ, Brazil.Abstract (Portuguese)
Este trabalho objetiva avaliar os resultados de medidas de perda de pressao efetuadas na experiencia DADINE com o Codigo RELAP4/MOD5; enquadrando-se no contexto de avaliacao teorico-experimental de codigos computacionais. A Instalacao DADINE permite medir experimentalmente a perda de pressao numa secao de teste tubular, de diametro hidraulico similar aqueles dos canais de refrigeracao dos reatores nucleares a agua leve pressurizada, sujeito as condicoes de escoamentos bifasicos existentes na fase de remolhamento de um acidente de perda de refrigerante primario por grande ruptura. Observou-se nesta avaliacao que o codigo RELAP4/MOD5 subestimou os dados experimentais, provavelmente devido ao calculo dos termos de perda de pressao por gravidade e atrito em escoamentos bifasicos. (autor)Additional details
Additional titles
- Original title (Portuguese)
- Comparacao da perda de pressao calculada pelo codigo RELAP4/MOD5 com resultados da experiencia DADINE
Publishing Information
- Imprint Title
- Proceedings of the 7. National Meeting of Reactor Physics and Thermohydraulic. v. 2
- Imprint Pagination
- 358 p.
- Journal Page Range
- p. 137-147.
Conference
- Title
- 7. National Meeting of Reactor Physics and Thermohydraulic.
- Dates
- 26-28 Apr 1989.
- Place
- Recife, PE (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 20061085
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; LOSS OF COOLANT; PRESSURE DROP; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; R CODES; REWETTING; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EVALUATION; FLUID FLOW; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Anais do 7. Encontro Nacional de Fisica de Reatores e Termohidraulica. v. 2.