연구동향 분석

On-line measurement and simulation of the in-core gamma energy deposition in the McMaster nuclear reactor

Mohammed Alqahtani 2022년

논문상세정보
인용/피인용
' On-line measurement and simulation of the in-core gamma energy deposition in the McMaster nuclear reactor' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
  • Gamma heating
  • Gamma thermometer
  • Irradiation site
  • fuelassembly
동일주제 총논문수 논문피인용 총횟수 주제별 논문영향력의 평균
16 0

0.0%

' On-line measurement and simulation of the in-core gamma energy deposition in the McMaster nuclear reactor' 의 참고문헌

  • a Time-dependent Description of In-Core Gamma Heating in the Mcmaster Nuclear Reactor
    K, Stoll [2016]
  • Understanding RTDs
  • The NJOY Nuclear Data Processing System
  • Serpent-2 and OSCAR-4 computational tools compared against McMaster nuclear reactor improved operational data history for U-235 fuel inventory tracking, local power tracking and validation of multiplication factor
  • OSCAR-4 CODE SYSTEM COMPARISON AND ANALYSIS WITH A FIRST-ORDER SEMI-EMPIRICAL METHOD FOR CORE-FOLLOW DEPLETION CALCULATION IN MNR
  • Nuclear Heating Measurements in Material Testing Reactor: A Comparison between a Differential Calorimeter and a Gamma Thermometer
  • New energy deposition treatment in the serpent 2 Monte Carlo transport code
    R. Tuominen [2019]
  • McMaster Nuclear Reactor Specification, IAEA CRP 1496: Innovative Methods for Research Reactors
  • Manual for reactor produced radioisotopes
    [2003]
  • Introduction to Nuclear Reactor Theory
  • In-core instrumentation for LWRs, presented at IAEA meeting on ”in-core instrumentation and in-situ measurements in connection with fuel behaviour
  • Implementing a photon physics model in serpent 2; fotonifysiikkamallin kehitt€aminen serpent 2-koodiin, G2 pro gradu, diplomity€o
  • For a better estimation of gamma heating in nuclearmaterial-testing reactors and associated devices : status and work plan from calculation methods to nuclear data
    M. Lemaire [2015]
  • Experimental measurement and Monte Carlo code simulation of the gamma heating at different irradiation sites in a nuclear research reactor
  • Expanding the use of serpent 2 to fusion applications:shut-down dose rate calculations
  • Evaluation of measurement data d guide to the expression of uncertainty in measurement
  • ENDF/B-VII. 1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data
  • ENDF-6 formats manual e data formats and procedures for the evaluated nuclear data files ENDF/B-VI, ENDF/B-VII and ENDF/B-VIII.
    A. Trkov [2018]
  • Development of a coupled neutron/photon transport mode in the serpent 2 Monte Carlo code, 2017, international conference on mathematics and computational methods applied to nuclear science and engineering, mamp;C
  • Delayed fission energy effect on LWR normal operation and transients
    Y. Liu [2018]
  • CUSTOMIZED IRRADIATION SITES FOR MEDICAL ISOTOPE PRODUCTION 50