Utilization of DRUFAN 01/MOD 02 computer code for the depressurization phase analysis of a postulated loss of coolant accident in Angra 2/3 Nuclear Power Plants
Description
The DRUFAN 01/Mod 2 developed by Gesellschaft fur Reaktorsicherheit (GRS) mbh to simulate thermohydraulic behavior of the primary circuit of PWR reactors, during the despressurization phase and initial refilling phase of loss of coolant accidents by great ruptures, is presented. The program simulates the system to be analysed by control volumes-concentrated parameters model - and it is based on numerical solution of conservation equations for mass of water, mass of vapor, quantities of motion and energy, and on the control volume homogeneity hypothesis. The possibilities of thermodynamic disequilibrium, determining mass transfer between liquid and vapor phases assuming that one saturated phase, are considered. The process of computer code implantation in the Honeywell Bull 64 DPS 7 system at CNEN, the modifications done into the program and the application to the despressurization phase analysis of a loss of coolant accident at Angra-2 and Angra-3 reactors are considered. (M.C.K.)
Availability note (English)
MF available from INIS under the Report Number.Abstract (Portuguese)
Apresenta-se o programa DRUFAN 01/Mod 2, desenvolvido pela Gesellschaft fur Reaktorsicherheit (GRS) mbh para simular o comportamento termohidraulico do circuito primario de reatores PWR, durante a fase de despressurizacao e a fase inicial de reenchimento de acidentes de perda de refrigerantes por grandes rupturas. O programa simula o sistema a ser analisado atraves de volumes de controle-modelo de parametros concentrados e e baseado na solucao numerica das equacoes de conservacao para a massa de agua, massa de vapor, quantidades de movimento e energia, e na hipotese de homogeneidade dos volumes de controle. Consideram-se os desequilibrios termo dinamicos, determinando-se a transferencia de massa entre as fases liquida e de vapor, sob a hipotese de que uma das fases se encontra em estado saturado. Descrevem-se o processo de implantacao do codigo no sistema Honeywell Bull 64 DPS 7 da CNEN, as modificacoes feitas no programa e a aplicacao para analise da fase de despressurizacao de um acidente por perda de refrigerante nas centrais de Angra-2 e Angra-3. (M.C.K.)Files
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Additional details
Additional titles
- Original title (Portuguese)
- Utilizacao do programa DRUFAN 01/MOD 02 para a analise da fase de despressurizacao de um acidente postulado de perda de refrigerante nas centrais nucleares de Angra 2/3
Publishing Information
- Imprint Pagination
- 47 p.
- Report number
- CNEN-DR-GAA--01/85
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 18076905
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- ANGRA-2 REACTOR; ANGRA-3 REACTOR; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; D CODES; DEPRESSURIZATION; HONEYWELL COMPUTERS; IMPLEMENTATION; LOSS OF COOLANT; MASS TRANSFER; PRIMARY COOLANT CIRCUITS; THERMODYNAMICS; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COMPUTERS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; FLUID FLOW; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS