Recommended values of the delayed neutron yield for: U-235; U-238 and Pu-239

Benchmarking ENDF/B-VII.1, JENDL-4.0 and JEFF-3.1.1 with MCNP6

“…There appears to be a more or less constant 700 pcm difference between JENDL-4.0 and JEFF-3.1.1 results, with ENDF/B-VII.1 in the middle. It was checked that this constant difference is not due to Al data, by performing calculations with JENDL-4.0 nuclear data, with only the data for 27 Al taken from JEFF-3.1.1.…”

Benchmark Results for Delayed Neutron Data

“…The last core had heterogeneous plutonium metal fuel with carbon/stainless-steel dilutions, and a steel reflector. Measured values for β eff are given in e.g., [7]. • SNEAK (cores 7A, 7B, 9C1, and 9C2)…”

“…To extend this work, we present in this article a list of systems for which measurements of β eff or α (see below) are reported. For the validation of the JEF-2.2 nuclear data library, many of these systems were also analysed [7]. We have also performed calculations of β eff and α using a recently developed Monte Carlo method [8], and using nuclear data from JEFF-3.0, ENDF/B-VI.8, and JENDL-3.3.…”

A new method for absolute measurement of βeff based on Microscopic Noise Experiments and the Two-Region model in the IPEN/MB-01 research reactor

“…Currently, all the β eff measurement techniques [4] cannot directly give the β eff , but they yield it using several calculated and/or semi-experimental parameters. Uncertainties of these parameters are critical uncertainty sources in these techniques.…”