Prismatic VHTR neutronic benchmark problems-Reference-Cited by-同舟云学术

Prismatic VHTR neutronic benchmark problems

Published:2015-04 Issue: Volume:285 Page:207-240
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Connolly Kevin John,Rahnema Farzad,Tsvetkov Pavel V.

Funder

NEUP Award Number

U.S. Department of Energy

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference11 articles.

1. Prismatic Coupled Neutronics/Thermal Fluids Transient Benchmark of the MHTGR-350 MW Core Design: Benchmark Definition;Gougar,2010

2. A Monte Carlo Based Nodal Diffusion Model for Criticality Analysis and Application of High-Order Cross Section Homogenization Method to Two-Group Nodal Diffusion;Ilas,2002

3. NGNP Preliminary Point Design – Results of the Initial Neutronics and Thermal-Hydraulic Assessments;MacDonald,2003

4. Compendium of Material Composition Data for Radiation Transport Modeling;McConn,2011

5. Evaluation of local power distribution with fine-mesh core model for high temperature engineering test reactor (HTTR);Murata;J. Nucl. Sci. Technol.,1994

Cited by 6 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. High-fidelity neutronics and thermal-hydraulics analysis of helical cruciform fuel based on small modular FHR;Progress in Nuclear Energy;2023-05

2. A SIMPLIFIED SMAHTR BENCHMARK PROBLEM SET;EPJ Web of Conferences;2021

3. A Stylized 3-D Benchmark Problem Set Based on the Pin-Fueled SmAHTR;Nuclear Technology;2020-07-09

4. COMET neutronics solutions to the prismatic VHTR benchmark problem;Nuclear Engineering and Design;2020-03

5. A Coarse-Mesh Coupled Neutronics and Thermal Fluids Method for Prismatic Cores;Nuclear Science and Engineering;2016-10