No abstract available

No abstract available

[en] Results of experimental studies carried out in two water models of size 1/24 and 1/15, to assess the free level fluctuation in the hot pool of PFBR are presented. The results when extrapolated to the prototype gives a ripple height of 50 mm. The results of thermal stratification studies carried out in 1/24 scale model, using hot and cold water indicates that the interface velocity can be correlated with the Richardson number. The paper also gives the details of computer codes developed for the estimation of flow and temperature fields in the pools. (author)

No abstract available

[en] High operating temperature (540degC), high temperature differentials and thermal shocks occurring in some of the components of the Prototype Fast Breeder Reactor (PFBR), produce both time-independent and time dependent inelastic deformations. The first part of the paper describes the design procedure using the 'elastic' routes of ASME code case N-47 and the French Code RCC-MR. Because of the conservatism in the code rules, sometimes it is not possible to meet them using elastic analysis, and detailed inelastic analysis, becomes necessary. The second part of the paper describes such an analysis carried out for PFBR inner vessel. (author). 5 refs., 16 figs

[en] A new test reactor facility, the STF, currently scheduled for criticality in 1982, is being designed by ANL to meet needs for increased testing capabilities in the U.S. fast reactor safety testing program. The reactor will provide a fast reactor neutron spectrum and prototypical radial and axial power profiles over a large central test region capable of accommodating full-size commercial LMFBR and GCFR fuel elements in test sizes up to the equivalent of several subassemblies. Extensive access for fuel-motion monitoring (including multiple neutron-hodoscopes) and other test-diagnostic equipment will be provided. Cost and schedule considerations have resulted in a burst-type heat-capacity design capable of delivering the energy equivalent of approximately 30 seconds of normal full-power test-fuel operation in arbitrary complex power-time shapes including short period power bursts

No abstract available

No abstract available

[en] One part of the LMFBR safety assurance program has been the testing to failure of prototypic fuel in a sodium environment. Effort has recently been applied toward development of a new Safety Test Facility (STF) which would provide improved testing capability. Alternative test reactor design work has been done on the Phoebus/Uhtrex design and the High Fluence Fast Pulse Reactor (HFFPR). As part of the HFFPR design effort, a criterion has been developed to allow rapid and inexpensive scoping analyses of different core designs, using zero-dimensional neutronics calculations. This paper derives this criterion and describes several promising core designs which were explored with this method

[en] The Reactor Protection System (RPS) brings the reactor into a safe shutdown state when an input parameter exceeds the threshold limits. The RPS comprises of the sensors detecting the events, the processing channels and the actual shutdown elements. This paper brings out the requirements of a reactor protection system, its design principles, compares various logics used in different reactors and ends with a proposed system for PFBR. (author). 8 refs., 1 tab., 3 figs