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Discussions are presented concerning integral experiments primarily on water and graphite systems. A description of experimental facilities is included along with details of die-away experiments, infinite-medium spectrum measurements, spatially dependent spectrum measurements, spectrum measurements for graphite systems, and development of a subcritical assembly program. (J.R.D.).
Nuclear Science and Technology, Volume 2: Neutron Physics provides information pertinent to neutron and reactor physics. This book presents a discussion of the general area of energy sources, surveying the fusion problem. Organized into 16 chapters, this volume starts with an overview of the broad range of other research related to nuclear technology, radiation effects, solid state work, chemistry, and materials research. This book then examines the experimental data for the cross sections and fission parameters of the fissile nuclides. Other chapters outline the role of fast choppers in time-of-flight spectrometers and consider the total cross section measurements. This book discusses as well the various experiments performed to test the operation of the system. The final chapter deals with the long-range prospects of fusion power. This book is a valuable resource for graduate students, physicists, nuclear engineers, researchers, scientists involved in fusion research will find this book extremely useful.
The Very High Temperature Reactor (VHTR), one of the Generation IV reactor concepts, is a helium-cooled, graphite-moderated nuclear reactor with a core temperature reaching 1000 & deg;C. It can provide high quality process heat for hydrogen production beside power generation and will become deployable around 2030. At such temperature, graphite is an appropriate neutron moderator material due to its high sublimation temperature and high temperature strength. Furthermore, graphite has a large heat capacity and stable structure due to its large thermal inertia. However, the current thermal neutron cross-section libraries of graphite are based on models and data developed in the 1950s and 1960s. Significant discrepancies between measurements and the computational predictions of these libraries were observed. As a result, a study was performed in this dissertation to benchmark modern and traditional thermal neutron scattering libraries of graphite. In this work, a Slowing-Down-Time experiment was designed and performed at the Oak Ridge National Laboratory (ORNL) by using the Oak Ridge Electron Linear Accelerator (ORELA) as a neutron source to study the neutron thermalization in graphite at room and higher temperatures. The MCNP5 code was utilized to simulate the detector responses and help optimize the experimental design including the size of the graphite assembly, furnace, shielding system and detector position. To facilitate such calculation, MCNP5 version 1.30 was modified to enable perturbation calculation using point detector type tallies. By using the modified MCNP5 code, the sensitivity of the experimental models to the graphite total thermal neutron cross-sections was studied to optimize the design of the experiment. Measurements of slowing-down-time spectrum in graphite were performed at room temperature for a 70x70x70 cm graphite pile by using a Li-6 scintillator and a U-235 fission counter at different locations. The measurements were directly compared to the M.