On the few-group cross-section generation methodology for PBR analysis-Reference-Cited by-同舟云学术

On the few-group cross-section generation methodology for PBR analysis

Published:2006-08 Issue:11-12 Volume:33 Page:1058-1070
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Ilas G.,Hudson N.H.,Rahnema F.,Ougouag A.M.,Gougar H.G.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference30 articles.

1. ANSWERS/WIMS, 1999. WIMS Version 8A User’s Guide. AEA Technology.

2. Bende, E., 1999. Plutonium Burning in a Pebble-Bed Type High Temperature Nuclear Reactor, Ph.D. Thesis, Delft University of Technology.

3. Analytical calculation of the average Dancoff factor for a fuel kernel in a pebble bed high-temperature reactor;Bende;Nuclear Science and Engineering,1999

4. Briesmeister, J.F., 1998. MCNP – A General Monte Carlo Code for Neutrons, Photons, and Electrons Transport, Version 4B2. Technical Report LA-12625-M, LANL.

5. Briesmeister, J.F., 2003. MCNP – A General Monte Carlo N-Particle Transport Code, Version 5. Technical Report LA-UR-03-1987, LANL.

Cited by 9 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. A review of multiphysics tools and methods to evaluate high temperature pebble bed reactors;Progress in Nuclear Energy;2024-06

2. Ordered Particle Packing in Dense TRISO/SiC Fuel Elements and Preliminary Assessment of Neutronic and Thermomechanical Characteristics;Nuclear Science and Engineering;2022-04-20

3. Two-Step Procedure for Liquid-Salt-Cooled-Reactor Analysis;Nuclear Technology;2018-07-17

4. Optimization of Thorium Utilization in Fluoride Salt-Cooled High-Temperature Reactor (FHR);Proceedings of The 20th Pacific Basin Nuclear Conference;2017

5. Equivalence treatment in homogenization via Monte Carlo method;Annals of Nuclear Energy;2016-06