Volume 137

Annals of Nuclear Energy

Volume 137

1

Review on neutronic/thermal-hydraulic coupling simulation methods for nuclear reactor analysis

Wang, Jincheng, Wang, Qin, Ding, Ming

Journal:

Annals of Nuclear Energy

Year:

2020

Language:

english

File:

PDF, 1.66 MB

english, 2020

2

DIAMOND – A Method of Characteristics neutron transport code using unstructured meshing

Jain, Lakshay, Karthikeyan, Ramamoorthy, Kannan, Umasankari

Journal:

Annals of Nuclear Energy

Year:

2020

Language:

english

File:

PDF, 4.27 MB

english, 2020

3

A note on the Chisholm parameter equation in RELAP

Journal:

Annals of Nuclear Energy

Year:

2020

Language:

english

File:

PDF, 240 KB

english, 2020

4

Transient thermal-hydraulic analysis for fuel assembly blockage accident by coupling CFD code with the neutron kinetics model

Wang, Lizhi, Jin, Ming, Wang, Lei, Zhang, Guangyu, Wu, Guowei

Journal:

Annals of Nuclear Energy

Year:

2020

Language:

english

File:

PDF, 2.28 MB

english, 2020

5

Uncertainty and sensitivity analysis of PWR mini-core transients in the presence of nuclear data uncertainty using non-parametric tolerance limits

Aures, A., Berner, N., Pautz, A., Zwermann, W.

Journal:

Annals of Nuclear Energy

Year:

2020

Language:

english

File:

PDF, 2.90 MB

english, 2020

6

Experimental study of droplet impacting on inclined wetted wall in corrugated plate separator

Chen, Bowen, Wang, Bo, Mao, Feng, Wen, Jiming, Tian, Ruifeng, Lu, Chuan

Journal:

Annals of Nuclear Energy

Year:

2020

Language:

english

File:

PDF, 2.54 MB

english, 2020

7

neutron transport

Hart, Nathan H., Azmy, Yousry Y., Duo, Jose I.

Journal:

Annals of Nuclear Energy

Year:

2020

Language:

english

File:

PDF, 10.09 MB

english, 2020

8

Radiotoxicity of minor actinides in thermal, epithermal and fast TMSRs with very high burnup

Zhang, Ao, Zou, Chunyan, Wu, Jianhui, Xia, Shaopeng, Yu, Chenggang, Chen, Jingen

Journal:

Annals of Nuclear Energy

Year:

2020

Language:

english

File:

PDF, 2.72 MB

english, 2020

9

Transient thermal-hydraulic analysis for fuel assembly blockage accident by coupling CFD code with the neutron kinetics model

Wang, Lizhi, Jin, Ming, Wang, Lei, Zhang, Guangyu, Wu, Guowei

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 2.28 MB

2020

10

Novel numerical solution to the fractional neutron point kinetic equation in nuclear reactor dynamics

Polo-Labarrios, M.A., Quezada-García, S., Espinosa-Paredes, G., Franco-Pérez, L., Ortiz-Villafuerte, J.

Journal:

Annals of Nuclear Energy

Year:

2020

Language:

english

File:

PDF, 742 KB

english, 2020

11

Novel numerical solution to the fractional neutron point kinetic equation in nuclear reactor dynamics

Polo-Labarrios, M.A., Quezada-García, S., Espinosa-Paredes, G., Franco-Pérez, L., Ortiz-Villafuerte, J.

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 742 KB

2020

12

Modelling the tapered geometry of real 3D unit cell of polish MARIA reactor in a rectangular prism diffusion code

Muszynski, Dominik, Andrzejewski, Krzysztof

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.91 MB

2020

13

Editorial Board

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 28 KB

2020

14

Verification of dry storage cask loading using monoenergetic photon sources

Miller, Cameron A., Geddes, Cameron G.R., Ludewigt, Bernhard A., Clarke, Shaun D., Pozzi, Sara A.

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 3.33 MB

2020