JENDL-4.0: A New Library for Nuclear Science and Engineering

Abstract

The fourth version of the Japanese Evaluated Nuclear Data Library has been produced in cooperation with the Japanese Nuclear Data Committee. In the new library, much emphasis is placed on the improvements of fission product and minor actinoid data. Two nuclear model codes were developed in order to evaluate the cross sections of fission products and minor actinoids. Coupled-channel optical model parameters, which can be applied to wide mass and energy regions, were obtained for nuclear model calculations. Thermal cross sections of actinoids were carefully examined by considering experimental data or by the systematics of neighboring nuclei. Most of the fission cross sections were derived from experimental data. A simultaneous evaluation was performed for the fission cross sections of important uranium and plutonium isotopes above 10 keV. New evaluations were performed for the thirty fissionproduct nuclides that had not been contained in the previous library JENDL-3.3. The data for light elements and structural materials were partly reevaluated. Moreover, covariances were estimated mainly for actinoids. The new library was released as JENDL-4.0, and the data can be retrieved from the Web site of the JAEA Nuclear Data Center.

Updated and revised neutron reaction data for237Np

“…2 between the evaluations and measurements. In general, present result agree well with the measurements [22,23] and JENDL-4.0 [4], and it is higher than ENDF/B-VII [5] Figure 3. Simplified reaction and decay scheme of 237 Np(n,2n) reaction (measured transitions are indicated as red arrow line).…”

“…The measurements are agree well with each other after analysis, evaluation and re-normalization to standard reaction cross section. The present evaluation consistent with ENDF/B-VII [5], JENDL-4.0 [4] and the measurements very well. Cross Sections (barn) Incident Neutron Energy (MeV) 237 Np(n, γ) Reaction Cross Section (Cor.)…”

“…The data of 237 Np in CENDL-3.1 [2] were revised in 2003, and there exist many new evaluations [3][4][5][6] and measurements on it, and the standard reaction cross sections [5] were updated in 2008. In the present work the data for 237 Np in CENDL-3.1 [2] are revised.…”

Transmutation of Long-Lived Nuclear Wastes

“…Table II shows the reduced half lives of some long-lived nuclides for some reactions. The nuclear data file JENDL-4.0 [2] was used for the calculation. 241 Am can be transmuted by threshold fission reaction induced by fast neurons (>1MeV).…”

Generation of Radioisotopes with Accelerator Neutrons by Deuterons

“…However, it is known that a charge exchange reaction, such as (n,p), (n,np þ d), and (n, ), of a sample nucleus with a medium-weight mass (<100) has a sizable cross section of from $50 to $500 mb at $10 < E n < 18 MeV. 29) Therefore, a wide variety of carrier-added and carrier-free radioisotopes (without any other isotope of a sample nuclide) can be produced using neutrons from the nat C(d,n) reaction at E d ¼ 40 MeV. In fact, we have proposed new routes to produce carrier-free medical radioisotopes of 90 Y, 30) 64 Cu, and 67 Cu 31) using fast neutrons from an accelerator.…”