Results 131 to 140 of about 25,004 (172)

Coupled Neutron and Gamma Heating Calculation Based on VARIANT Transport Solutions

Nuclear science and engineering, 2019
For accurate assessment of nuclear heating in fast reactors, a new coupled neutron and gamma heating calculation scheme has been developed based on VARIANT nodal transport solutions of neutron and gamma flux distributions.
P. Deng, B. Jeon, H. Park, W. Yang
semanticscholar   +1 more source

CALCULATION OF THE PARAMETERS OF STOCHASTIC NEUTRON KINETICS IN ZERO POWER NUCLEAR REACTORS

PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS, 2019
The majority of neutron-physical problems of nuclear power plants design can be solved on the basis of various approximations to the Boltzmann transport equation in terms of the averaged characteristics of the reactor: the effective multiplication factor,
E. Zemskov, K. Melnikov, I. Tormyshev
semanticscholar   +1 more source

Structural Aspects of Neutron Survival Probabilities

Journal of Nuclear Engineering
The neutron survival probability (and related quantities including probabilities of extinction and initiation) is a central element of the broader stochastic theory of neutron populations and finds application in fields including reactor start-up ...
Scott D. Ramsey
semanticscholar   +1 more source

Methods and applications of 3-D SN neutron transport code ATES3

Life Cycle Reliability and Safety Engineering, 2023
Anurag Gupta
semanticscholar   +1 more source

The measurement of the thermal neutron absorption cross sections of graphite and carbon by W. Bothe and P. Jensen – a recalculation of the experiments and the graphite problem during the early uranium work

Kerntechnik
The experiments of W. Bothe and P. Jensen from the year 1940 to determine of the thermal neutron absorption cross sections of graphite and carbon were recalculated with current neutron transport codes and latest nuclear data in order to find out the ...
Hans Brockmann
semanticscholar   +1 more source

A re-visitation of space asymptotic theory in neutron transport

The European Physical Journal Plus, 2020
S. Dulla, P. Ravetto
semanticscholar   +2 more sources

Development and Initial Analysis of a Neutron Diffusion Model for TEPLATOR Using COMSOL Multiphysics Software

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology
The growing demand for sustainable energy solutions has stimulated the advancement of novel reactor technologies like TEPLATOR, a small modular reactor conceptualized by a collaborative team of researchers from the University of West Bohemia (UWB) and ...
Dipanjan Ray, M. Lovecký, J. Zavorka, R. Škoda   +3 more
semanticscholar   +1 more source

Thermal Cut-Off Energy for Accurate Analysis of Prismatic High-Temperature Gas-Cooled Reactor

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology
In this study, the appropriate thermal cut-off energy for neutron transport calculations in High-Temperature Gas-cooled Reactor (HTGR) is investigated.
S. Takeda, T. Kitada, Akio Yamamoto, K. Yamaji, Hiroki Koike, Koji Asano   +5 more
semanticscholar   +1 more source

Evaluation of Expansion Reactivity Based on Reactivity Coefficient for Sodium-Cooled Fast Reactor

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology
In this paper, formulas for evaluating expansion reactivity based on reactivity coefficients in sodium-cooled fast reactors are derived, and the approximation errors used in the derivation are also evaluated.
S. Takeda, T. Kitada, E. Hoashi, T. Okita   +3 more
semanticscholar   +1 more source

High-Fidelity Depletion-Pebble-Flow Coupling Simulation of Pebble Bed Reactor HTR-PM

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology
The high-fidelity depletion and pebble-flow coupling simulation of pebble bed reactor is realized based on Monte Carlo (MC) and Discrete Element Method (DEM).
Ruihan Li, Jingang Liang, Ding She, Weijian Zhang   +3 more
semanticscholar   +1 more source