Preparation of a Cross Section Library for a 3 MW Triga Reactor and its Validation through Some Applications

A data base for the TRIGAP code has been generated for the 3 MW TRIGA Mark II reactor, Bangladesh, using the WIMS-D/4 code. Cross sections were calculated from zero burnup to 37% of initial 235U in 20 burnup steps. The created TRIGAP library was tested and compared with experimental values or with values in the Safety Analysis Report (SAR). Excellent agreement of calculated values of temperature defect, flux distribution, temperature coefficient and peaking factor with experimental values establishes the validity of the library.