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Journal ArticleDOI

Japanese evaluated nuclear data library version 3 revision-3: JENDL-3.3

TLDR
JENDL-3.2 as discussed by the authors is the most recent version of JENDL 3.1.2, which is based on the feedback information of various benchmark tests and includes the resonance parameters, capture and inelastic scattering cross sections, and fission spectra.
Abstract
The revision work of JENDL-3 has been made by considering feedback information of various benchmark tests. The main revised quantities are the resonance parameters, capture and inelastic scattering cross sections, and fission spectra of main actinide nuclides, the total and inelastic scattering cross sections of structural materials, the resonance parameters the capture and inelastic scattering cross sections of fission products, and the γ-ray production data. The revised data were released as JENDL-3.2 in June 1994. The preliminary benchmark tests indicate that JENDL-3.2 predicts various reactor characteristics more successfully than the previous version of JENDL-3.1.

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Journal ArticleDOI

Geant4—a simulation toolkit

S. Agostinelli, +126 more
TL;DR: The Gelfant 4 toolkit as discussed by the authors is a toolkit for simulating the passage of particles through matter, including a complete range of functionality including tracking, geometry, physics models and hits.
Journal ArticleDOI

Recent developments in GEANT4

John Allison, +102 more
TL;DR: Geant4 as discussed by the authors is a software toolkit for the simulation of the passage of particles through matter, which is used by a large number of experiments and projects in a variety of application domains, including high energy physics, astrophysics and space science, medical physics and radiation protection.
Journal ArticleDOI

ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data

TL;DR: The ENDF/B-VII.1 library as mentioned in this paper is the most widely used data set for nuclear data analysis and has been updated several times over the last five years. But the most recent version of the ENDF-B-VI.0 library is based on the JENDL-4.0 standard.
Journal ArticleDOI

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

TL;DR: The fourth version of the Japanese Evaluated Nuclear Data Library has been produced in cooperation with the Japanese Nuclear Data Committee as mentioned in this paper, and much emphasis is placed on the improvement of the original library.
References
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MCNP-A General Monte Carlo N-Particle Transport Code

TL;DR: In this article, the authors present a practical guide for the use of general-purpose Monte Carlo code MCNP, including several examples and a discussion of the particular techniques and the Monte Carlo method itself.

Prompt fission neutron spectra and average prompt neutron multiplicities

D.G. Madland, +1 more
TL;DR: In this article, the authors present a new method for calculating the prompt fission neutron spectrum N(E) and average prompt neutron multiplicity anti nu/sub p/ as functions of the fissioning nucleus and its excitation energy.
Journal ArticleDOI

New Calculation of Prompt Fission Neutron Spectra and Average Prompt Neutron Multiplicities

TL;DR: In this article, the prompt fission spectrum N(E) as a function of both the fissioning nucleus and its excitation energy was calculated on the basis of standard nuclear evaporation theory.
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