Abstract
For analyzing the safety evaluation of solvent fire as DBA in an extraction process of nuclear fuel reprocessing plant, computer code named FACE was developed in JAERI under the auspices of the Science and Technology Agency of Japan. The code FACE can provide not only for calculations of temperature, pressure, flow rate and pressure drop in cells and ducts of the network in air-ventilation system by one- and two-dimensional analyses and smoke containing radioactive materials by burning solvent in the network but also for solvent fire behavior in the cell, transport of radioactive materials and its deposition in the network, integrity of HEPA filters, and release of radioactive materials to the environment. Calculations by FACE were compared with data obtained by large-scale demonstration tests in JAERI simulating solvent fire in the extraction process to verify mathematical modeling of the fire accident in the code. (author).
Nishio, Gunji;
[1]
Yamazaki, Noboru
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Nishio, Gunji, and Yamazaki, Noboru.
Safety analysis of solvent fire accidents in a fuel reprocessing plant.
Japan: N. p.,
1991.
Web.
Nishio, Gunji, & Yamazaki, Noboru.
Safety analysis of solvent fire accidents in a fuel reprocessing plant.
Japan.
Nishio, Gunji, and Yamazaki, Noboru.
1991.
"Safety analysis of solvent fire accidents in a fuel reprocessing plant."
Japan.
@misc{etde_10109167,
title = {Safety analysis of solvent fire accidents in a fuel reprocessing plant}
author = {Nishio, Gunji, and Yamazaki, Noboru}
abstractNote = {For analyzing the safety evaluation of solvent fire as DBA in an extraction process of nuclear fuel reprocessing plant, computer code named FACE was developed in JAERI under the auspices of the Science and Technology Agency of Japan. The code FACE can provide not only for calculations of temperature, pressure, flow rate and pressure drop in cells and ducts of the network in air-ventilation system by one- and two-dimensional analyses and smoke containing radioactive materials by burning solvent in the network but also for solvent fire behavior in the cell, transport of radioactive materials and its deposition in the network, integrity of HEPA filters, and release of radioactive materials to the environment. Calculations by FACE were compared with data obtained by large-scale demonstration tests in JAERI simulating solvent fire in the extraction process to verify mathematical modeling of the fire accident in the code. (author).}
place = {Japan}
year = {1991}
month = {Sep}
}
title = {Safety analysis of solvent fire accidents in a fuel reprocessing plant}
author = {Nishio, Gunji, and Yamazaki, Noboru}
abstractNote = {For analyzing the safety evaluation of solvent fire as DBA in an extraction process of nuclear fuel reprocessing plant, computer code named FACE was developed in JAERI under the auspices of the Science and Technology Agency of Japan. The code FACE can provide not only for calculations of temperature, pressure, flow rate and pressure drop in cells and ducts of the network in air-ventilation system by one- and two-dimensional analyses and smoke containing radioactive materials by burning solvent in the network but also for solvent fire behavior in the cell, transport of radioactive materials and its deposition in the network, integrity of HEPA filters, and release of radioactive materials to the environment. Calculations by FACE were compared with data obtained by large-scale demonstration tests in JAERI simulating solvent fire in the extraction process to verify mathematical modeling of the fire accident in the code. (author).}
place = {Japan}
year = {1991}
month = {Sep}
}