NJOY2016 updates for ENDF/B-VIII.0

This paper presents the application of the MCNP5 code to conduct a modification design and simulation of a thermal neutron beam for neutron capture studies at the Dalat Nuclear Research Reactor (DNRR). The designed configuration of the horizontal neutron channel No.2 at the DNRR, which contains a conical collimator of 240.3 cm in length, and neutron filters of crystal Al2O3 and Bi with alternative thickness, were simulated. A pure thermal neutron beam can be obtained at the irradiation position when a composition of crystal filter of 20 cm Al2O3 and 6 cm Bi is employed. The thermal and epithermal neutron fluxes are 1.02´108 n/cm2/s (account for 97.92% of total neutron flux) and 0.22´107 n/cm2/s (account for 2.08% of total neutron flux), respectively.

show abstract

“…4. The neutron total cross-sections of Al 2 O 3 and Si crystal filters are prepared by using the NJOY16 code [12], as shown in Fig. 5.…”

Section: Methodsmentioning

confidence: 99%

Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor

Tu¹,

Dang

Ngoc³

et al. 2023

Comm. in Phys.

View full text Add to dashboard Cite

show abstract

“…Attempting to read older libraries, such as ENDF71SaB can lead to errors, however, as some of the provided discrete cosines are outside the [−1, 1] interval. The only solution to this problem is to generate new ACE files for these evaluations, as this problem has been fixed in more recent versions of NJOY2016 [35].…”

Section: Library Verificationmentioning

confidence: 99%

Papillon Nuclear Data Library – a free and open-source C++/Python library for interacting with ACE files for continuous-energy neutron data

Belanger

2023

EPJ Nuclear Sci. Technol.

View full text Add to dashboard Cite

In this paper, a new C++ and Python library, called the Papillon Nuclear Data Library, is presented. This library gives users a simple interface to read and interact with continuous-energy neutron data in the form of ACE files. Using the library, one can easily evaluate or plot cross-sections for different nuclides and reactions, or sample scattering distributions. Currently, all continuous-energy neutron physics is implemented, and the library can read free-gas neutron and thermal scattering law ACE files. The Python interface makes using nuclear data easy and accessible for students, while the C++ interface gives experienced researchers easy access to continuous-energy physics when writing Monte Carlo codes to test new computational methods.

show abstract

“…Since the latest MCPLIB was generated using the ENDF/B VI.8 data, the photon KERMA factor and photo-atomic interaction cross section of the MC 2 -3 gamma library were generated using the ENDF/B VI.8 data for the comparison with MCNP while the neutron KERMA factor and prompt photon production matrix were generated using the ENDF/B VII.0 data. The latest NJOY2016 [19] was used in this study while NJOY99.v393 was used in preparing the original library. It was observed that the NJOY version change from NJOY99.v393 to NJOY2016 affects the heating of three isotopes listed in Table 3.4.…”

Section: Library Generation For Verification Testsmentioning

confidence: 99%

Verification and Validation Tests of the Gamma Library of the ARC Software Package (Rev.1)

Park¹,

Yang²,

Smith³

et al. 2022

View full text Add to dashboard Cite

show abstract

NJOY2016 updates for ENDF/B-VIII.0

Cited by 4 publications

References 0 publications

Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor

Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor

Papillon Nuclear Data Library – a free and open-source C++/Python library for interacting with ACE files for continuous-energy neutron data

Verification and Validation Tests of the Gamma Library of the ARC Software Package (Rev.1)

Contact Info

Product

Resources

About