Reference 1-GWe D-T reactors; tokamak TR-1, spherical tokamak ST-1 and helical HR-1 reactors, are designed using PEC (Physics Engineering Cost) code, and thier plasma behaviors with Internal Transport Barrier (ITB) operations are analyzed using TOTAL (Toroidal Transport Analysis Linkage) code, which clarifies the requirement of deep penetration of pellet fueling to realize steady-state advanced...

Decay heat (DH) is the produced through a radioactive decay of fission products during or after reactor operation. It known as second largest source power in core fission. Being such strong contributor to power, it should be accurately determined at any time Currently, there are two main approaches for DH estimation used simulation codes. One approach based on careful inventorying all target nu...

In a typical pressurized water reactor, neutron detectors located outside the reactor core monitor power. addition, they are also used to measure reactivity of control rods. A novel approach calculate ex-core detector response in using Monte Carlo technique is presented. detailed model Krško nuclear power plant was developed transport code MCNP. Due location detectors, hybrid ADVANTG generate v...

The Molten Salt Reactor Experiment (MSRE), which operated at Oak Ridge National Laboratory from 1965 to 1969, was an experimental reactor that used UF4 fuel dissolved in molten fluoride salt. Criticality achieved when the salt mixture passed through graphite-moderated core region. Therefore, because and fission products flowed system, delayed neutron precursors were not confined core, decay hea...

A method is proposed for determining power-density profiles in nuclear reactor fuel rods from neutron flux measurements obtained by multiple in-core micropocket fission detectors (MPFD). A general formulation is presented that relates the power-density profiles in a reactor’s fuel rods to the flux density at detector locations. Key to this formulation is the construction of an appropriate respo...

The direct measurement of plutonium in spent reactor fuel is an unmet challenge in international safeguards. In this simulation study, we investigate the use of the delayed gamma rays from fission product nuclei to determine the amount of fissile isotopes (Pu-239, Pu-241, and U-235) in irradiated light water reactor fuel assemblies. Fission is stimulated with an interrogating neutron source, an...

Abstract Z-Pinch fusion centre, encased by a fission envelope, serves as an individual neutron source. It can expeditiously catalyze reactions in 238U and 232Th nuclear materials, which are hard to use current commercial reactors. This is the essence of Driven Fusion-Fission Hybrid Reactor (Z-FFR). The core acts stand-alone source, efficiently driving energy materials that difficult existing re...

Pressurized water reactors are typically surrounded in the radial direction by neutron reflectors made from stainless steel and water. These decrease leakage provide protection of pressure vessel fast neutrons damaging its integrity. Such a reflector influences multiplication factor core distribution flux fission power inside core. All these effects can be analyzed full-core simulations using m...

We show a new system named AZCATL-CRP to design full power control rod patterns in BWRs. Azcatl-CRP uses an ant colony system and a reactor core simulator for this purpose. Transition and equilibrium cycles of Laguna Verde Nuclear Power Plant (LVNPP) reactor core in Mexico were used to test Azcatl-CRP. LVNPP has 109 control rods grouped in four sequences and currently uses control cell core (CC...