POSCA: A computer code for fission product plateout and circulating coolant activities within the primary circuit of a high temperature gas-cooled reactor
Author:
Funder
Nuclear R&D Program of the NRF of Korea
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference22 articles.
1. Plate-out fission products and its effect on maintenance and repair;Iniotakis;Nucl. Eng. Des.,1984
2. A study of plateout fission product behavior during a large-scale pipe rupture accident in a high-temperature gas-cooled reactor;Sawa;Nucl. Technol.,1994
3. Fuel Performance and Fission Product Behaviour in Gas Cooled Reactor,1997
4. Plateout Phenomena in Direct-Cycle High Temperature Gas-Cooled Reactors;Hanson,2002
5. A review of radionuclide behaviour in the primary system of a very-high-temperature reactor;Kissane;Nucl. Eng. Des.,2009
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