HEXERE12: computer program for the transient thermal-hydraulic analysis of high temperature gas-cooled reactors

Mapping Intimacies ◽

10.2172/7219032 ◽

1977 ◽

Author(s):

G.E. Giles ◽

W.D. Turner ◽

K.W. Childs ◽

R.M. DeVault ◽

B.R. Becker

Keyword(s):

High Temperature ◽

Computer Program ◽

Hydraulic Analysis ◽

Transient Thermal ◽

Thermal Hydraulic Analysis ◽

High Temperature Gas

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HEXEREI: a multi-channel heat conduction convection code for use in transient thermal hydraulic analysis of high-temperature, gas-cooled reactors. Interim report

10.2172/7348284 ◽

1976 ◽

Author(s):

G Giles ◽

R DeVault ◽

W Turner ◽

B Becker

Keyword(s):

Heat Conduction ◽

High Temperature ◽

Interim Report ◽

Hydraulic Analysis ◽

Transient Thermal ◽

Thermal Hydraulic Analysis ◽

High Temperature Gas

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A Steady-State Thermal-Hydraulic Analysis Method for Prismatic High-Temperature Gas-Cooled Reactors

Nuclear Technology ◽

10.13182/nt15-14 ◽

2016 ◽

Vol 193 (2) ◽

pp. 234-246 ◽

Cited By ~ 1

Author(s):

A. J. Huning ◽

S. Garimella ◽

F. Rahnema

Keyword(s):

Steady State ◽

High Temperature ◽

Analysis Method ◽

Hydraulic Analysis ◽

Thermal Hydraulic Analysis ◽

High Temperature Gas

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RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume II. Program implementation. [PWR and BWR]

10.2172/7349742 ◽

1976 ◽

Author(s):

Not Given Author

Keyword(s):

Computer Program ◽

Program Implementation ◽

Nuclear Reactors ◽

Hydraulic Analysis ◽

Transient Thermal ◽

Thermal Hydraulic Analysis

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RELAP4: a computer program for transient thermal-hydraulic analysis

10.2172/4351327 ◽

1973 ◽

Cited By ~ 11

Author(s):

K Moore ◽

W Rettig

Keyword(s):

Computer Program ◽

Hydraulic Analysis ◽

Transient Thermal ◽

Thermal Hydraulic Analysis

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ICONE23-1474 DESIGN AND THERMAL-HYDRAULIC ANALYSIS OF SUPERCRITICAL STEAM GENERATOR IN HIGH-TEMPERATURE GAS-COOLED REACTOR

The Proceedings of the International Conference on Nuclear Engineering (ICONE) ◽

10.1299/jsmeicone.2015.23._icone23-1_216 ◽

2015 ◽

Vol 2015.23 (0) ◽

pp. _ICONE23-1-_ICONE23-1

Author(s):

Zhen ZHANG ◽

Xing-tuan YANG ◽

Huai-ming JU

Keyword(s):

High Temperature ◽

Steam Generator ◽

Hydraulic Analysis ◽

Thermal Hydraulic Analysis ◽

High Temperature Gas

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COBRA IIIC: digital computer program for steady state and transient thermal-hydraulic analysis of rod bundle nuclear fuel elements

10.2172/4480166 ◽

1973 ◽

Cited By ~ 45

Author(s):

D.S. Rowe

Keyword(s):

Steady State ◽

Computer Program ◽

Nuclear Fuel ◽

Digital Computer ◽

Hydraulic Analysis ◽

Rod Bundle ◽

Transient Thermal ◽

Fuel Elements ◽

Thermal Hydraulic Analysis

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RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume III. Checkout applications. [PWR and BWR]

10.2172/7146110 ◽

1976 ◽

Author(s):

C. F. Obenchain ◽

J. H. Ramsthaler ◽

E. P. Eales ◽

T. R. Charlton ◽

F. W. Childs ◽

...

Keyword(s):

Computer Program ◽

Nuclear Reactors ◽

Hydraulic Analysis ◽

Transient Thermal ◽

Thermal Hydraulic Analysis

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COBRA-III: A DIGITAL COMPUTER PROGRAM FOR STEADY STATE AND TRANSIENT THERMAL--HYDRAULIC ANALYSIS OF ROD BUNDLE NUCLEAR FUEL ELEMENTS.

10.2172/4711911 ◽

1971 ◽

Cited By ~ 6

Author(s):

D.S. Rowe

Keyword(s):

Steady State ◽

Computer Program ◽

Nuclear Fuel ◽

Digital Computer ◽

Hydraulic Analysis ◽

Rod Bundle ◽

Transient Thermal ◽

Fuel Elements ◽

Thermal Hydraulic Analysis

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THREE-DIMENSIONAL MODELING AND THERMAL HYDRAULIC ANALYSIS OF HIGH TEMPERATURE GAS-COOLED REACTOR CORE

The Proceedings of the International Conference on Nuclear Engineering (ICONE) ◽

10.1299/jsmeicone.2019.27.1788 ◽

2019 ◽

Vol 2019.27 (0) ◽

pp. 1788

Author(s):

Shuangbao Zhang ◽

Liangxing Li ◽

Wei Xie ◽

Kailin Wang

Keyword(s):

High Temperature ◽

Three Dimensional ◽

Reactor Core ◽

Hydraulic Analysis ◽

Three Dimensional Modeling ◽

Dimensional Modeling ◽

Thermal Hydraulic Analysis ◽

High Temperature Gas

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Thermal hydraulic analysis of a pebble-bed modular high temperature gas-cooled reactor with ATTICA3D and THERMIX codes

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2012.02.014 ◽

2012 ◽

Vol 246 ◽

pp. 286-297 ◽

Cited By ~ 18

Author(s):

Yanhua Zheng ◽

J. Lapins ◽

E. Laurien ◽

L. Shi ◽

Z. Zhang

Keyword(s):

High Temperature ◽

Hydraulic Analysis ◽

Pebble Bed ◽

Thermal Hydraulic Analysis ◽

High Temperature Gas

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