The Influence of Energy Group Structure and Nonlinearities on the Calculation of Xenon-Induced Flux Oscillations

1983 ◽  
Vol 83 (1) ◽  
pp. 149-161 ◽  
Author(s):  
J. D. Teachman ◽  
R. J. Onega
Keyword(s):  
Group Structure ◽  
Energy Group

Neutron Up-Scattering Effect in Refined Energy Group Structure

2016 ◽  
Author(s):  
Qingming He ◽  
Hongchun Wu ◽  
Yunzhao Li ◽  
Liangzhi Cao ◽  
Tiejun Zu
Keyword(s):  
Cross Sections ◽  
Group Structure ◽  
Scattering Matrix ◽  
The Self ◽  
Shielding Effect ◽  
Doppler Broadening ◽  
Fuel Temperature ◽  
Energy Group ◽  
Scattering Effect ◽  
Mc Method

Aiming at generating a 361-group library, this paper investigated neutron up-scattering effect in the 361-group Santamarina-Hfaiedh Energy Mesh (SHEM). Firstly, the Doppler Broadening Rejection Correction (DBRC) method is implemented to consider the neutron up-scattering effect in Monte Carlo (MC) method. Then the MC method is employed to prepare resonance integral table and scattering matrix for afterward calculation. Numerical results show that the neutron up-scattering affects kinf by ∼200 pcm at most for UO2 pin cell problems in the 361-group SHEM, while the fuel temperature coefficient (FTC) is also influenced by 12∼13%. It has also been found that both of the above two influences acts through scattering matrix rather than self-shielded absorption cross sections. In addition, the self-shielding effect of cladding is studied and it’s been found that it affects kinf by 30∼70 pcm.

Optimising the energy group structure used for fusion systems

2013 ◽  
Vol 55 ◽  
pp. 108-115 ◽  
Author(s):  
L. Morgan ◽  
J.-C. Sublet ◽  
W. Haeck ◽  
J. Pasley
Keyword(s):  
Group Structure ◽  
Fusion Systems ◽  
Energy Group

scholarly journals GENERATION AND INITIAL VALIDATION OF A NEW CASMO5 ENDF/B-VIII.0 NUCLEAR DATA LIBRARY

2021 ◽  
Vol 247 ◽  
pp. 09001
Author(s):  
Rodolfo Ferrer ◽  
Joel Rhodes
Keyword(s):  
State Of The Art ◽  
Group Structure ◽  
Nuclear Data ◽  
Fission Rate ◽  
Energy Group ◽  
Initial Validation ◽  
Satisfactory Performance ◽  
Nuclear Data Library ◽  
Data Library ◽  
Generation Procedure

A new nuclear data library for the CASMO5 advanced lattice physics code has been generated based on the recently-released ENDF/B-VIII.0 evaluation. The ENDF/B-VIII.0 evaluation represents the state-of-the-art in nuclear data and features new evaluations from the CIELO project for 1H, 16O, 56Fe, 235U, 238U and 239Pu. A description of the library generation procedure used to process these data into the CASMO5 586 energy group structure is provided. Initial validation of the new ENDF/B-VIII.0-based library, referred to as the E8R0 library, is also presented and involves the comparison of predicted k–eff and fission rate distributions to measurements from various critical experiments. The critical experiments used in the initial validation of the E8R0 library consist of the B&W 1810 series, B&W 1484 series, DIMPLE S06A/B, and TCA reflector experiment with iron plates. The results from the initial validation indicate that the new E8R0 library provides a satisfactory performance in terms of CASMO5 predicted k–eff and fission distributions.

An optimization approach to establish an appropriate energy group structure for BWR pin-by-pin core analysis

2012 ◽  
Vol 49 (7) ◽  
pp. 689-707 ◽  
Author(s):  
Tatsuya Fujita ◽  
Kenichi Tada ◽  
Tomohiro Endo ◽  
Akio Yamamoto ◽  
Shinya Kosaka ◽  
...  
Keyword(s):  
Group Structure ◽  
Optimization Approach ◽  
Core Analysis ◽  
Energy Group

Study on Calculation Difference of the SCWR Core Steady-State Analysis Code

2020 ◽  
Vol 6 (3) ◽  
Author(s):  
Lianjie Wang ◽  
Lei Yao ◽  
Ping Yang ◽  
Di Lu ◽  
Wenbo Zhao
Keyword(s):  
Steady State ◽  
Cross Section ◽  
Power Distribution ◽  
Group Structure ◽  
Three Dimensional ◽  
Thermal Hydraulics ◽  
Steady State Analysis ◽  
Energy Group ◽  
The Cross ◽  
State Analysis

Abstract The three-dimensional code system supercritical water-cooled reactor (SCWR) coupled neutronics/thermal-hydraulics analysis (SNTA) code is developed for SCWR core steady-state analysis by coupling neutronics/thermal-hydraulics (N/T). This paper studies the calculation difference between the SNTA code and the standard reactor analysis code (SRAC). By using the impacts exclusive method, it is confirmed that the calculation difference between these two codes is caused by different feedback of the cross section. The cross section data and the energy group structure of the SRAC code differ from the SNTA code, and the density coefficient of reactivity calculated by the SRAC code is higher, which means the feedback of the density and power distribution is bigger and the axial power distribution varies rapidly. The SNTA code with finer energy group structure is suitable for the performance analysis of SCWR core which has strong N/T coupling characteristics.

scholarly journals A study on improving the performance of a research reactor's equilibrium core

2013 ◽  
Vol 28 (4) ◽  
pp. 362-369
Author(s):  
Atta Muhammad ◽  
Masood Iqbal ◽  
Tayyab Mahmood
Keyword(s):  
Cross Sections ◽  
Group Structure ◽  
Energy Group ◽  
Time Cycle ◽  
Computer Codes ◽  
Fission Neutrons ◽  
Improved Performance ◽  
Enriched Uranium ◽  
Fuel Elements ◽  
Uranium Silicide

Utilizing low enriched uranium silicide fuel (U3Si2-Al) of existing uranium density (3.285 g/cm3), different core configurations have been studied in search of an equilibrium core with an improved performance for the Pakistan Research Reactor-1. Furthermore, we have extended our analysis to the performance of higher density silicide fuels with a uranium density of 4.0 and 4.8 U g/cm3. The criterion used in selecting the best performing core was that of ?unit flux time cycle length per 235U mass per cycle?. In order to analyze core performance by improving neutron moderation, utilizing higher-density fuel, the effect of the coolant channel width was also studied by reducing the number of plates in the standard/control fuel element. Calculations employing computer codes WIMSD/4 and CITATION were performed. A ten energy group structure for fission neutrons was used for the generation of microscopic cross-sections through WIMSD/4. To search the equilibrium core, two-dimensional core modelling was performed in CITATION. Performance indicators have shown that the higher-density uranium silicide-fuelled core (U density 4.8 g/cm3) without any changes in standard/control fuel elements, comprising of 15 standard and 4 control fuel elements, is the best performing of all analyzed cores.

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