Description
Chairs: Andrei Rineiski and Koji Morita
Fast Flux Test Facility (FFTF) was a research Sodium-cooled Fast Reactor (SFR) operated in the 1980’s with a goal to demonstrate the inherent and passive safety characteristics of the SFR design. In the frame of this study, an attempt has been made to develop a model of the FFTF suitable to predict the system’s behavior during the Unprotected Loss of Flow (ULOF) accident. In particular,...
Severe accident source term problem is the calculation of transport and release of radionuclides (RNs) from the reactor core to the environment for a hypothetical accident sequence of low probability. Generally, the source term problem is decoupled into four source terms: 1) In-vessel source term, 2) Interface source term 3) In-containment source term and 4) Environmental source term.
In...
Three Work Packages (WPs) were defined in this Coordinated Research Project (CRP) whose objective was to estimate fission-product-transportation behaviour inside the reference pool-type sodium-cooled fast reactor (SFR) volumes (i.e., in-primary vessel, cover gas system and in-containment building) at different time scales under severe accident conditions. This WP, WP-2, is defined to estimate...
The main objective of the coordinated research project (CRP) on is to simulate the fission product transportation behavior of the reference pool-type sodium-cooled fast reactor (SFR) of 1250 MWth capacity with mixed oxide fuel under severe accident conditions. The accident considered is an unprotected loss of flow accident resulting in a core damage event with release of radionuclides. The...
The accident at the Fukushima NPP (Japan) showed that the design of the power unit should consider the unforeseen excess of the external influence intensity. The accidents for internal reasons can be predicted on the basis of knowledge and it depends, first of all, on the designers approach, but it is impossible to foresee catastrophic external influences.
This method is proposed the heat...
The Fast Breeder Test Reactor (FBTR) at Kalpakkam is the flagship of the second stage of the three-stage nuclear program of Department of Atomic Energy in India. Health physics services commenced at FBTR in April 1985 itself and the reactor went critical in October 1985. FBTR is a unique reactor utilizing U-Pu C as the fuel. Presently, FBTR has been operated upto a maximum power of 32 MW(t)...
The small modular sodium-cooled fast reactor (SFR) is an important component of Generation-IV reactors. For SFR, one type beyond design basis accidents (BDBA) that has received special attention is the anticipated transients without scram (ATWS) events including unprotected loss of coolant flow (ULOF) accident, unprotected loss of heat sink (ULOHS) accident and unprotected transient overpower...
The Versatile Test Reactor (VTR) is a fast spectrum test reactor currently being developed in the United States under the direction of the US Department of Energy (USDOE), Office of Nuclear Energy. The mission of the VTR is to enable accelerated testing of advanced reactor fuels and materials required for advanced reactor technologies. The conceptual design of the 300 MWth sodium-cooled...
