The basic structure of a reactor physics laboratory environment simulation software, developed using object modeling technique (OMT), and based on the reactor point kinetic equation, is presented. Also, various capabilities of the simulator in teaching the fundamental concepts of reactor physics are discussed. &#10 In this virtual laboratory, student can perform seven different experiments...

Reactor vessel internals are structures located within the reactor vessel that support and orient the reactor fuel assemblies and direct coolant flow through the core. The core basket is part of the internals structure, which consists of vertical plates that surround the outer faces of the hexagonal peripheral fuel assemblies. The vertical plates are bolted to the edges of horizontal former pla...

One of the requirements of a future Fissile Material Cutoff Treaty is that fissile material used in naval reactor fuel must not be diverted for weapons purposes. This could become relevant for both weapon and non-weapon states of the NPT because, in both cases, the geometry of the fuel and core may be considered sensitive information. Inspections and measurements would therefore have to rely on...

The direct measurement of the chemistry in reactor cores is extremely difficult. The extreme conditions of high temperature, pressure, and radiation fields, are not compatible with normal chemical instrumentation. There are also problems of access to fuel channels in the reactor core. For these reasons, all reaction vendors and many operators have extensively used theoretical calculations and c...

Vaporization of fission products and certain other materials is estimated for the extreme environmental conditions projected for severe reactor accidents. Partial pressures of gaseous species are calculated from thermochemical data or estimates. Mounts of vapor transported material are evaluated from projected gas flows during two phases of a hypothetical accident--( a) core dry out phase and (...

The modified out-in fuel management strategy was applied to the core loading design for the first four cycles of the Bushehr (Iran-1) KWU designed Pressurized Water Reactor (PWR). The minimum peak-to-average power density was chosen as the objective function of the optimization process. Lattice homogenization and group constants generation were performed by using the LEOPARD computer code. For ...

A RELAP5-3D model has been developed for the RBMK Kursk 1 NPP. The primary features of this model are the three-dimensional neutronics model of the reactor core and the user subroutine that generates the neutron cross-sections. This subroutine contains the same neutron cross-section libraries that are presently being used in the Russian STEPAN/KOBRA calculations. The implementation of the neutr...