Development of One Group Constant Library for the Computer Code ORIGEN-2 Using JENDL-3.2
Yoshitaka Naito · Journal of Nuclear Science and Technology · 2002
Standard one group constant libraries for the ORIGEN-2 code are prepared using JENDL-3.2 for calculating the amount of nuclides generated in spent fuel of BWR, PWR and FBR, and the adaptability of the libraries is examined for the safety evaluation of the nuclear fuel cycle. This task is performed as a part of the activities of the nuclide generation evaluation working group of Japanese Nuclear Data Committee.