Installation of aerosol behavior model into multi-dimensional thermaI hydraulic analysis code AQUA

; Yamaguchi, Akira

PNC TN9410 98-028, 33 Pages, 1997/12

PNC-TN9410-98-028.pdf:0.93MB

The safety analysis of FBR plant system for sodium leak phenomena needs to evaluate the deposition of the aerosol particle to the components in the plant, the chemical reaction of aerosol to humidity in the air and the effect of the combustion heat through aerosol to the structural component. For this purpose, ABC-INTG (Aerosol Behavior in Containment-INTeGrated Version) code has been developed and used until now. This code calculates aerosol behavior in the gas area of uniform temperature and pressure by 1 cell-model. Later, however, more detailed calculation of aerosol behavior requires the installation of aerosol model into multi-cell thermal hydraulic analysis code AQUA. AQUA can calculate the carrier gas flow, temperature and the distribution of the aerosol spatial concentration. On the other hand, ABC-INTG can calculate the generation, deposition to the wall and flower, agglomeration of aerosol particle and figure out the distribution of the aerosol particle size. Thus, the combination of these two codes enables to deal with aerosol model coupling the distribution of the aerosol spatial concentration and that of the aerosol particle size. AQUA and ABC-INTG were developed separately, therefore, several subroutine were modified and composed. Especially, the interface program which exchanges data between these two codes is important to execute transient calculation. This report describes aerosol behavior model, how to install the aerosol model to AQUA and new subroutine equipped to the code. Furthermore, the test calculations of the simple structural model were executed by this code, appropriate results were obtained. Thus, this code has prospect to predict aerosol behavior by the introduction of coupling analysis with multi-dimensional gas thermo-dynamics for sodium combustion evaluation.

None

PNC TJ1647 97-001, 131 Pages, 1997/02

PNC-TJ1647-97-001.pdf:2.29MB

no abstracts in English

Studies of fuel coolant interactions during core melt accident of nuclear power plants

Yamano, N.; Sugimoto, Jun; Maruyama, Yu; Soda, Kunihisa

NUREG/CP-0127, 0, p.271 - 281, 1993/00

no abstracts in English

Performance of containment sprays for light water reactors and evaluation of the heat transfer

; ; ; ; ; ;

Nuclear Technology, 54, p.54 - 67, 1981/00

https://doi.org/10.13182/NT81-A32753

no abstracts in English

Behavior of sodium oxide aerosol in a closed chamber

; ; ; ;

Journal of Nuclear Science and Technology, 10(9), p.566 - 573, 1973/09

https://doi.org/10.3327/jnst.10.566

no abstracts in English

Development of a function calculating deposition probabilities of inhaled aerosols compatible with the revised Human Respiratory Tract Model

Manabe, Kentaro; Takahashi, Fumiaki

no journal, , 

A dose estimation system which integrates external and internal exposure is being developed to contribute to radiation protection for members of the public from radionuclides released into the environment. For internal exposure, inhalation of radioactive aerosols should be considered, and internal doses by inhalation depend on their diameters, densities, shape. However, dose coefficients published by the International Commission on Radiological Protection (ICRP) are developed with the assumption that distribution of particle diameters has a specific log-normal distribution. In addition, the existing codes can consider only a single value or a log-normal distribution for diameters of particles and do not fit the divisions of particle deposition determined by the revised Human Respiratory Tract Model (revised HRTM). Therefore, we developed a function of the dose estimation system which can calculate deposition fractions of inhaled particles having a given diameter distribution, density, and shape factor using the deposition model of ICRP. This function reproduced the deposition fractions for adult males in a light exertion level. In future, this function will be put in the dose estimation system to calculate internal dose coefficients under various conditions.