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Argonne’s NSTF: Active testing of passive cooling
A facility at Argonne National Laboratory has been simulating nuclear reactor cooling systems under a wide range of conditions since the 1980s. Its latest task, described by Argonne in an August 13 news release, is testing the performance of passive safety systems for new reactor designs.
Designed as a half-scale model of a real reactor system, Argonne’s Natural Convection Shutdown Heat Removal Test Facility (NSTF) is used for large-scale experimental testing of the performance of passive safety systems, which are designed to remove decay heat using natural forces including gravity and heat convection. Those tests yield benchmarking data qualified to the level of National Quality Assurance-1 (NQA-1) that is shared with vendors and regulators to validate computational models and guide licensing of new reactors and components.
Om Prakash Joneja, J.-P. Schneeberger, Vijay R. Nargundkar
Fusion Science and Technology | Volume 23 | Number 4 | July 1993 | Pages 400-407
Technical Paper | Blanket Engineering | doi.org/10.13182/FST93-A30132
Articles are hosted by Taylor and Francis Online.
Integral tritium production rate (TPR) measurements are important in comparisons of calculations to ascertain the suitability of computer codes and cross-section sets used in calculation. At the LOTUS facility, one of the objectives is to make measurements with different types of pure fusion and hybrid blankets and compare the results with calculations. Since the concrete cavity housing the blankets is small, it is of direct relevance to determine the influence of room-reflected neutrons on the integral TPR and, if possible, to reduce this effect by special absorbers. The effects on the TPR of a stainless steel—natural lithium—graphite-reflected blanket due to the concrete structure, B4C filter, and boron-loaded sheets covering the assembly are studied. Calculations are performed by the MCNP Monte Carlo code. Since the room-returned component depends strongly on the composition of the concrete and, moreover, does not correspond to a real blanket situation, it is advisable to compare measurements with calculations for the region where such interference is minimal. A central region measuring 30.15 × 26.25 × 60 cm3 is identified for the purpose of comparison. In addition to calculations for a fully homogenized blanket, the important central blanket region is considered in the form of rods, and the remaining blanket as a homogeneous region, to assess the effect of neutron streaming on the TPR of the assembly. An experiment is done by irradiating several Li2CO3 probes positioned in each tube so that the central region of interest is fully covered. The activity of the probes is measured by the standard liquid scintillation method, and the TPR for the entire region can be derived from the experimental reaction rate data. The complete details of the calculational model and the experimental procedure are provided. Good agreement is found between the calculated and experimental TPRs after accounting for various sources of errors. This suggests that the three-dimensional description of the source and the blanket arrangement employed for the calculations are quite satisfactory.