Evaluation of core nuclear analysis code system for LMR using measured physics parameters of BFS-73-1 critical assembly

As the first stage of the critical experiment plan for developing the Korea Advanced LIquid MEtal Reactor (KALIMER) core design, the basic neutronics characteristics of the BFS-73-1 critical assembly representing a uranium metal fueled benchmark core were investigated. The prediction capability of the core nuclear analysis code system, being developed as a standard analysis system in the KALIMER core design and analysis, has been evaluated against the BFS- 73-1 experiment by comparing the calculated results to the measurements. The comparison shows that the e€ective multiplication factor was overpredicted by 0.3%in the C/E value. The 235U and 238U fission reaction rate distributions were underpredicted within a 2% discrepancy in the core region but appeared to be in poor agreement in the blanket region. The calculated values of spectral indices at the core center and the e€ective delayed neutron fraction, eff , agreed with the measured ones within 2% and 1% discrepancies, respectively. The first order perturbation method predicted the sample reactivity worths for 235U, 238U, 239Pu and 10B within 7%but much larger discrepancies existed for the other materials. The calculated Doppler e€ect showed about an 8%overprediction