reactor core pajwuers calculation by two -group theory

Two-group Reactor Noise Analysis by Langevin’s Technique

Beam calculation for TRIGA reactor

As part of the INIE project of the Big-10 consortium, efforts are underway at UIUC to assemble and test a set of codes that can be used for the design of the next generation of research reactor. SCALE 4.4 has been selected as one of the set of codes for this purpose. We here report some results of analysis of a TRIGA reactor using KENOVI, one of the codes in the SCALE system. Results are presen...

Thermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model

Thermal hydraulics of nuclear reactor as a basis of reactor safety has a very important role in reactor design and control. The thermal-hydraulic analysis provides input data to the reactor-physics analysis, whereas the latter gives information about the distribution of heat sources, which is needed to perform the thermal-hydraulic analysis. In this study single heated channel model as a very f...

Calculation of UNil for the cyclic group of order two

Cappell’s unitary nilpotent groupsUNil∗(R; R,R) are calculated for the integral group ring R = Z[C2] of the cyclic groupC2 of order two. Specifically, they are determined as modules over the Verschiebung algebra V using the Connolly–Ranicki isomorphism [CR05] and the Connolly–Davis relations [CD04]. 2000 Mathematics Subject Classification: 57R67; 19J25.

Core Loading Design for Bushehr Pressurized Water Reactor

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 ...

Reactor Physics Analysis of the VHTGR Core

As part of an I-NERI project to develop safety analysis codes and experimental validation for a VeryHigh Temperature Gas-Cooled Reactor (VHTGR), we have developed MCNP5 [1] models to represent material heterogeneities inherent in the microsphere fuel particles and fuel compacts for a GT-MHR design [2]. We have also performed preliminary coupled nuclear-thermalhydraulic (NTH) analysis to obtain ...