The Decay Data Evaluation Project (DDEP) and the JEFF-3.3 radioactive decay data library: Combining international collaborative efforts on evaluated decay data

Abstract

Abstract. The Decay Data Evaluation Project (DDEP), is an international collaboration of decay data evaluators formed with groups from France, Germany, USA, China, Romania, Russia, Spain and the UK, mainly from the metrology community. DDEP members have evaluated over 220 radionuclides, following an agreed upon methodology, including a peer review. Evaluations include all relevant parameters relating to the nuclear decay and the associated atomic processes. An important output of these evaluations are recommendations for new measurements, which can serve as a basis for future measurement programmes. Recently evaluated radionuclides include:

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

“…However, various shortcomings, both in content and evaluation methodology, led to the establishment of a new decay data evaluation system developed through the JEFF project. The initial construction of the JEFF-3.0 decay data sub-library [4] used the most recent versions of the NUBASE [318] and Evaluated Nuclear Structure Data File (ENSDF) [301] databases, complemented with specialised decay data evaluations from the United Kingdom Activation Product Decay Data (UKPADD) and Heavy Element and Actinide Decay Data (UKHEDD) libraries [319], the Decay Data Evaluation Project (DDEP) [320], the IAEA Actinide Decay Data Library [321] and the International Reactor Dosimetry and Fusion File (IRDFF) [252]. The different data sources are sequentially processed with various quality checks, e.g.…”

Dissecting Reactor Antineutrino Flux Calculations

“…In our calculations a) reactor start-up/shut-down and fuel storage effects were not applied, b) the Z m (Q, ∆Q) functions are from Eq. (7) using the JEFF-3.1 fission yields [27] and updated ENDF/B-VII.1 decay data [28], c) some Q m values were fixed to those of main contributors such as 96 Y and 92 Rb, d) conversion calculations were also performed on summation electron spectra to check for biases [29], e) for 238 U we used the summation method with the same set of fission yields and decay data, f) IBD cross sections are from Ref. [32], g) C exp was taken as 1.…”

Effects of Fission Yield Data in the Calculation of Antineutrino Spectra forU235(n,fission)a

“…Currently there are two distinct sets of recommended fission yield data, the ENDF/B-VII.1 [24] and the JEFF-3.1 [25] libraries, which provide independent and cumulative fission yields for ground state (g.s.) and isomeric levels.…”