Interaction between the radiative flux emitted by a corium melt and aerosols from corium/concrete interaction
Creators
- 1. CEA-DRN/DER/SERA - CE Cadarache, Saint-Paul-Lez-Durance (France)
- 2. Univ. of Wisconsin, Madison, WI (United States)
Description
In this paper we present a one-dimensional numerical model that deals with radiative transfer in a medium where aerosols are present. This model is written with the aim of performing radiative transfer calculations in the framework of severe Pressurized Water Reactor accidents, especially during the last stage of such an accident Molten Core Concrete Interaction (MCCI) when aerosols are very numerous. We explain the theoretical basis of our model, writing the general radiative transfer equation, knowing that aerosol droplets participate in radiation transport. We then simplify this equation for a one-dimensional medium and we propose to solve it using the spherical harmonics approximation. This gives us the radiative intensity and we can then deduce the radiative flux. Aerosol optical properties (extinction and scattering coefficients) are also required in such a calculation. They are determined using Rayleigh or Mie theory, depending, depending on the aerosol size. In order to provide an example of results one can expect from such a calculation, we applied our model to a test problem with given aerosol size and concentration distributions. Our example does not model any experiment explicitly but the physical conditions used are very close to the L4 test from the Advanced Containment Experiment (ACE) program
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7, Volume 3, Sessions 12-16
- Imprint Pagination
- 1001 p.
- Journal Page Range
- p. 1797-1808.
- Report number
- NUREG/CP--0142-Vol.3
Conference
- Title
- 7. international meeting on nuclear reactor thermal hydraulics.
- Dates
- 10-15 Sep 1995.
- Place
- Saratoga, NY (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27019704
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AEROSOLS; CONCRETES; CORIUM; FUEL-COOLANT INTERACTIONS; HYDRAULICS; MATHEMATICAL MODELS; RADIATION EFFECTS; RADIATION TRANSPORT; RADIATIVE COOLING; REACTOR SAFETY; SAFETY ANALYSIS; WATER COOLED REACTORS
- Descriptors DEC
- BUILDING MATERIALS; COLLOIDS; COOLING; DISPERSIONS; MATERIALS; REACTORS; SAFETY; SOLS
Optional Information
- Secondary number(s)
- CONF-950904--Vol.3.