Advantages of mesh tallying in MCNP5 for soil analysis calculations

被引：5
|
作者：
Doron, O. [1 ]
Wielopolski, L. [2 ]
Biegalski, S. [1 ]
机构：
[1] Univ Texas Austin, Univ Stn 1, Austin, TX 78759 USA
[2] Brookhaven Natl Lab, Dept Environm Sci, Upton, NY 11973 USA
来源：
JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY | 2008年 / 276卷 / 01期
关键词：
Linear Regression Line; Soil Volume; Neutron Generator; Monte Carlo Code; Individual Tally;
D O I：
10.1007/s10967-007-0430-8
中图分类号：
O65 [分析化学];
学科分类号：
070302 ; 081704 ;
摘要：
The Monte Carlo code, MCNP5, includes a mesh and lattice tally option useful for large matrix calculations. Recently, a fast lattice tally (FLT) was developed for MCNPX. We used these two codes to model an in-situ soil analysis system based on inelastic neutron scattering. The tallies were utilized to calculate the reaction rates of fast neutrons with carbon via inelastic reactions. The results of these three tallies and their respective computational times are compared, and the advantages of these methodologies discussed.
引用
收藏
页码：183 / 186
页数：4
相关论文
共 50 条
  • [21] Technical Note: Improved implementation of doppler broadening in MCNP5
    Bartol, Laura J.
    DeWerd, Larry A.
    MEDICAL PHYSICS, 2012, 39 (09) : 5635 - 5638
  • [22] 基于MCNP5软件的中子屏蔽模拟
    彭凤梅
    魏强林
    刘义保
    电脑与电信, 2012, (Z1) : 68 - 70
  • [23] Convergence Assessment of the MCNP5 Model for NUR Research Reactor
    Mokhtari, O.
    Mazrou, H.
    1ST INTERNATIONAL CONFERENCE ON RADIATIONS AND APPLICATIONS (ICRA-2017), 2018, 1994
  • [24] Effects of element composition in soil samples on the efficiencies of gamma energy peaks evaluated by the MCNP5 code
    Vu Ngoc Ba
    Bui Ngoc Thien
    Truong Thi Hong Loan
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2021, 53 (01) : 337 - 343
  • [25] Characteristics of multiprocessing MCNP5 on small personal computer clusters
    Robinson, S. M.
    McConn, R. J., Jr.
    Pagh, R. T.
    Schweppe, J. E.
    Siciliano, E. R.
    JOURNAL OF INSTRUMENTATION, 2006, 1
  • [26] Extensions of the MCNP5 and TRIPOLI4 Monte Carlo Codes for Transient Reactor Analysis
    Hoogenboom, J. Eduard
    Sjenitzer, Bart L.
    SNA + MC 2013 - JOINT INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS + MONTE CARLO, 2014,
  • [27] Simulation of a new neutron calibration laboratory in Brazil using MCNP5
    Morero, Lucas Dadalt
    Pereira, Walsan Wagner
    Borges, Jose Carlos
    Nicolucci, Patricia
    APPLIED RADIATION AND ISOTOPES, 2022, 186
  • [28] MCNP5 modelling of HPGe detectors for efficiency evaluation in -ray spectrometry
    Maurotto, A.
    Rizzo, S.
    Tomarchio, E.
    RADIATION EFFECTS AND DEFECTS IN SOLIDS, 2009, 164 (5-6): : 302 - 306
  • [29] Criticality and rod worth analysis of the DNRR research reactor using the SRAC and MCNP5 codes
    Quang Binh Do
    Phan, Giang T. T.
    Kien-Cuong Nguyen
    Quang Huy Ngo
    Hoai-Nam Tran
    NUCLEAR ENGINEERING AND DESIGN, 2019, 343 : 197 - 209
  • [30] A COMPARISON OF BETA SKIN DOSES CALCULATED WITH VARSKIN 5.35.3 AND MCNP5
    Dubeau, J.
    Witharana, S. S. Hakmana
    Sun, J.
    Heinmiller, B. E.
    Chase, W. J.
    RADIATION PROTECTION DOSIMETRY, 2018, 182 (04) : 502 - 507
12345