Continuous Energy Monte Carlo Calculations of Randomly Distributed Spherical Fuels in High-Temperature Gas-Cooled Reactors Based on a Statistical Geometry Model-Reference-Cited by-同舟云学术

Continuous Energy Monte Carlo Calculations of Randomly Distributed Spherical Fuels in High-Temperature Gas-Cooled Reactors Based on a Statistical Geometry Model

Published:1996-05 Issue:1 Volume:123 Page:96-109
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Murata Isao¹,Mori Takamasa¹,Nakagawa Masayuki¹

Affiliation:

1. Japan Atomic Energy Research Institute, Naritacho 3607, Oarai-machi Higashiibaraki-gun, Ibaraki-ken, 311-13, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE96-A24215

Reference35 articles.

1. S. SAITO et al. “Design of High Temperature Engineering Test Reactor,” JAERI-1332, Japan Atomic Energy Research Institute (1994).

2. R. SHINDO, K. YAMASHITA, and I. MURATA, “DELIGHT-7; One Dimensional Fuel Cell Burnup Analysis Code for High Temperature Gas-Cooled Reactor (HTGR),” JAERI-M 90-048, Japan Atomic Energy Research Institute (1990).

3. The Resonance Integral of Coated Particles

Cited by 45 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. Simplified Treatment of Coating Layers in TRISO Fuel in Statistical Geometry Method in Monte Carlo Calculation;Nuclear Science and Engineering;2024-08-28

2. Chord length sampling correction analysis for dispersion fuel in Monte Carlo simulation;Nuclear Science and Techniques;2024-04

3. Chord length sampling with memory effects for spatially heterogeneous Markov media: Application to the rod model;Physical Review E;2024-03-19

4. Deterministic Transport Calculation Method for Statistical Geometry with Small Fuel Particles;Nuclear Science and Engineering;2023-08-08

5. Application of neutron current method for Dancoff factor estimation of fuel particles in double-heterogeneous fuel;Journal of Nuclear Science and Technology;2023-07-16