ORNL Research Reactor

In the course of study to evaluate the radiation field that would result from criticality accidents, a series of calculations was made to simulate a variety of critical systems. As a part of the study, an attempt was made to establish the validity of the computational method by calculating systems for which experimental data existed. Experiments involving highly enriched uranium metal systems were most plentiful due to the extensive experiments involving the Godiva reactor at Los Alam< National Laboratory (LANL) and the Healthy Physics Research Reactor at Oak Ridge National Laboratory (ORNL). Measurement had also been made with a hi y enriched uranium solution that simulated one of the early criticality accidents. The search, however, revealed that while critical experiments existed for low-enriched uranium solution systems, no radiation field measurements had been made for these systems. ... 

P. R. Kasten et al.,. Aqueous Homogeneous Research Reactor-Feasibility Study, USAEC Report ORNL-2256, Oak Ridge National Laboratory, April 1957. 

With India s well-known program involving heavy water reactors and fast breeders, their early involvement with MSR development is surprising to some. The Bhabha Atomic Research Centre (BARC) was involved with official collaborations with ORNL from 1969 to 1975 on MSBR research. Facilities were built based on salt chemistry and, in particular, studies carried out on PuFj solubility remain of great value today (Venugopal, 2013). The 2013 Conference on Molten Salts in Nuclear Technology (CMSNT) held at BARC detailed India s renewed interest in a wide variety of MSR and FHR concepts (http //moltensaltindia. org/speakers-presentations/). 

The development of the FUJI-series MSR is thoroughly based on the research and development (R D) results previously obtained in ORNL (USA) [XXX-1]. Many major reactor engineering problems have been clarified or solved until now. The MSRE successfully operated at ORNL in 1965-1969. The FUJI MSR has basically the same reactor core structure as the MSRE. 

ORNL, in W.R. Grimes (Ed.), Chemical Research and Development for the Molten-Salt Breeder Reactor, ORNL/TM-1853, Oak Ridge, TN, USA, 1967. 

C. H. Secoy et al., in Homogeneous Reactor Project Quarterly Progress Report for the Period Ending July SI, 1957, USAEC Report ORNL-2379, Oak Ridge National Laboratory, Oct. 10, 1957 (p. 163) F. Moseley, Core Solution Stability in the Homogeneous Aqiieous Reactor The Effect of Corrosion Product and Copper Concentrations, Report HARD(C)/P-41, Gt. Brit. Atomic Energy Research Establishment, May 1957. 

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