scholarly journals REFERENCE MANUAL FOR ENDF THERMAL NEUTRON SCATTERING DATA.

1968 ◽  
Author(s):  
J.U. Koppel ◽  
D.H. Houston
Keyword(s):  
Neutron Scattering ◽  
Thermal Neutron ◽  
Scattering Data ◽  
Thermal Neutron Scattering ◽  
Reference Manual

scholarly journals Thermal neutron scattering data for 7LiF and BeF2

2017 ◽  
Vol 146 ◽  
pp. 13009
Author(s):  
Jia Wang ◽  
Hongzhou Song ◽  
Zehua Hu ◽  
Tao Ye ◽  
Weili Sun
Keyword(s):  
Neutron Scattering ◽  
Thermal Neutron ◽  
Scattering Data ◽  
Thermal Neutron Scattering

Validation of ENDF/B-VIII thermal neutron scattering data of heavy water by differential cross section measurements at various temperatures

2020 ◽  
Vol 135 ◽  
pp. 106932 ◽  
Author(s):  
G. Li ◽  
G. Bentoumi ◽  
K. Hartling ◽  
I. Molnar ◽  
C. Neggers ◽  
...  
Keyword(s):  
Differential Cross Section ◽  
Neutron Scattering ◽  
Thermal Neutron ◽  
Cross Section ◽  
Heavy Water ◽  
Differential Cross ◽  
Scattering Data ◽  
Thermal Neutron Scattering

On-the-Fly Treatment of Discrete Representation Thermal Neutron Scattering Data in RMC Code

2020 ◽  
Author(s):  
Lei Zheng ◽  
Kaiwen Li ◽  
Kan Wang
Keyword(s):  
Elastic Scattering ◽  
Neutron Scattering ◽  
Thermal Neutron ◽  
Interpolation Method ◽  
Beryllium Oxide ◽  
Scattering Data ◽  
Computational Time ◽  
Discrete Representation ◽  
Thermal Region ◽  
Thermal Neutron Scattering

Abstract A proper treatment of thermal neutron scattering data is required for the high-fidelity neutronics calculation of thermal reactors. Monte Carlo codes typically use an S(α, β) treatment to describe scattering events in the thermal region if the S(α, β) data is available for the material. The S(α,β) model stores a large majority of scattering physics and can handle thermal scattering process accurately. In neutronic-thermohydraulic coupling calculations, the temperature effect on nuclear data must be treated properly. The on-the-fly sampling method or the on-the-fly interpolation method are typically used in thermal region. In this paper, the on-the-fly interpolation method for the discrete representation S(α,β) data was introduced. The two-dimensional linear-linear interpolation was used to calculate the scattering cross sections and the secondary information for inelastic scattering, coherent elastic scattering and incoherent elastic scattering. The implemented on-the-fly capability was tested by a series of benchmarks that contain various thermal materials, including light water, beryllium and beryllium oxide. The integral kinf eigenvalues, the efficiency and the fine energy spectra of the on-the-fly treatment capacity were compared with those of the references. Results show that the on-the-fly treatment capability has high accuracy, and the computational time increases up to 20%.

Development and application of temperature-dependent thermal neutron scattering data of light water for compensated neutron logging

2015 ◽  
Vol 27 (7) ◽  
pp. 74003
Author(s):  
王新华 Wang Xinhua ◽  
裴宇阳 Pei Yuyang ◽  
阳剑 Yang Jian
Keyword(s):  
Neutron Scattering ◽  
Thermal Neutron ◽  
Scattering Data ◽  
Temperature Dependent ◽  
Light Water ◽  
Thermal Neutron Scattering

scholarly journals Investigation of thermal neutron scattering data for BeF2and LiF crystals

2013 ◽  
Vol 50 (4) ◽  
pp. 419-424 ◽  
Author(s):  
Longwei Mei ◽  
Xiangzhou Cai ◽  
Dazhen Jiang ◽  
Jingen Chen ◽  
Wei Guo ◽  
...  
Keyword(s):  
Neutron Scattering ◽  
Thermal Neutron ◽  
Scattering Data ◽  
Thermal Neutron Scattering

scholarly journals Effect of FLiBe thermal neutron scattering on reactivity of molten salt reactor

2020 ◽  
Vol 239 ◽  
pp. 14008
Author(s):  
Yafen Liu ◽  
Wenjiang Li ◽  
Rui Yan ◽  
Yang Zou ◽  
Shihe Yu ◽  
...  
Keyword(s):  
Neutron Scattering ◽  
Thermal Neutron ◽  
Molten Salt ◽  
Liquid Fuel ◽  
Volume Ratio ◽  
Scattering Data ◽  
Maximum Effect ◽  
Molten Salt Reactor ◽  
Thermal Neutron Scattering ◽  
Thorium Molten Salt Reactor

Thermal neutron scattering data has an important influence on the calculation and design of reactor with a thermal spectrum. However, as the only liquid fuel in the Gen-IV reactor candidates, the research on the thermal neutron scattering effect of coolant and somewhat moderator FLiBe has not been carried out sufficiently either experimentally or theoretically. The effect of FLiBe thermal neutron scattering on reactivity of TMSR-LF (thorium molten salt reactor - liquid fuel), TMSR-SF (thorium molten salt reactor - solid fuel) and MSRE (molten salt reactor experiment) were investigated and compared. Results show that the effect of FLiBe thermal neutron scattering on reactivity depends to some extent on the fuel-graphite volume ratio of core. Calculations indicate that FLiBe thermal neutron scattering of MSRE (with the hardest spectrum) has the minimum effect of 41 pcm on reactivity, and FLiBe thermal neutron scattering of TMSR-SF (with the softest spectrum) has the maximum effect of -94 pcm on reactivity, and FLiBe thermal neutron scattering of TMSR-LF has an effect of -61 pcm on reactivity at 900 K.

scholarly journals ON-THE-FLY INTERPOLATION OF CONTINUOUS TEMPERATURE-DEPENDENT THERMAL NEUTRON SCATTERING DATA IN RMC CODE

2021 ◽  
Vol 247 ◽  
pp. 09012
Author(s):  
Lei Zheng ◽  
Zhiyuan Feng ◽  
Kan Wang
Keyword(s):  
Neutron Scattering ◽  
Thermal Neutron ◽  
Interpolation Method ◽  
Linear Interpolation ◽  
Scattering Data ◽  
High Fidelity ◽  
Continuous Representation ◽  
Pressurized Water ◽  
Secondary Neutron ◽  
Thermal Neutron Scattering

Thermal neutron scattering data have an important influence on the high-fidelity neutronics calculation of thermal reactors. Due to the limited storage capabilities of computers, a discrete ACE representation of the secondary neutron energy and angular distribution has been used for Monte Carlo calculation since the early 1980s. The use of this discrete representation does not produce noticeable effects in the integral calculations such as keff eigenvalues, but can produce noticeable deficiencies for differential calculations. A new continuous representation of the thermal neutron scattering data was created in 2006, but was not widely known. Recently, the continuous representation of the thermal neutron scattering ACE data based on ENDF/B-Ⅷ.0 library was officially released and was available for all users. The new representation shows great difference compared with the discrete one. In order to utilize the more physical and rigorous representation data for high fidelity neutronic-thermohydraulic coupling calculation, the on-the-fly treatment capability was proposed and implemented in RMC code. The two-dimensional linear-linear interpolation method was used to calculate the inelastic scattering cross sections and the secondary neutron energies and angles. The on-the-fly treatment capability was tested by a pressurized water reactor assembly. Results show that the on-the-fly treatment capability has high accuracy, and can be used to consider the temperature feedback in the neutronic-thermohydraulic coupling calculations. However, the efficiency of the on-the-fly treatment still need to be improved in the near future.

scholarly journals A New On-the-Fly Sampling Method for Incoherent Inelastic Thermal Neutron Scattering Data in MCNP6

2014 ◽  
Author(s):  
Andrew Pavlou ◽  
Forrest Brown ◽  
Wei Ji
Keyword(s):  
Neutron Scattering ◽  
Thermal Neutron ◽  
Sampling Method ◽  
Scattering Data ◽  
Thermal Neutron Scattering

scholarly journals A New On-the-Fly Sampling Method for Incoherent Inelastic Thermal Neutron Scattering Data in MCNP6

2014 ◽  
Author(s):  
Andrew Theodore Pavlou ◽  
Forrest B. Brown ◽  
Wei Ji
Keyword(s):  
Neutron Scattering ◽  
Thermal Neutron ◽  
Sampling Method ◽  
Scattering Data ◽  
Thermal Neutron Scattering
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