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Volume 170

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Nuclear Technology / Volume 170 / Number 1

April 2010

Table of Contents

Nuclear Technology / Volume 170 / Number 2

May 2010

Table of Contents

Nuclear Technology / Volume 170 / Number 3

June 2010

Foreword: Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants

Samim Anghaie

Nuclear Technology / Volume 170 / Number 1 / Page 1

April 2010

An Assessment of Large-Eddy Simulation Toward Thermal Fatigue Prediction

A. K. Kuczaj, E. M. J. Komen

Nuclear Technology / Volume 170 / Number 1 / Pages 2-15

April 2010

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Thermal-Fluid Characterizations of ZnO and SiC Nanofluids for Advanced Nuclear Power Plants

In Cheol Bang, Ji Hyun Kim

Nuclear Technology / Volume 170 / Number 1 / Pages 16-27

April 2010

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Condensation Correlation for a Vertical Passive Condenser System

Shripad T. Revankar, Seungmin Oh, Wenzhong Zhou, Gavin Henderson

Nuclear Technology / Volume 170 / Number 1 / Pages 28-39

April 2010

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Summary for Three Different Validation Cases of Coolant Flow in Supercritical Water Test Sections with the CFD Code ANSYS CFX 11.0

Attila Kiss, Attila Aszódi

Nuclear Technology / Volume 170 / Number 1 / Pages 40-53

April 2010

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Parametric Sensitivity Study on the Reflooding Models of the MARS Code Based on 6 × 6 Rod Bundle Test Results

Ki-Yong Choi, Seok Cho, Hyoung-Kyu Cho, Chul-Hwa Song

Nuclear Technology / Volume 170 / Number 1 / Pages 54-67

April 2010

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The Enhancements and Testing for the MCNPX 2.6.0 Depletion Capability

Michael L. Fensin, John S. Hendricks, Samim Anghaie

Nuclear Technology / Volume 170 / Number 1 / Pages 68-79

April 2010

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Development of an Automated Testing System for Verification and Validation of Nuclear Data and Simulation Code

Brian S. Triplett, Samim Anghaie, Morgan C. White

Nuclear Technology / Volume 170 / Number 1 / Pages 80-89

April 2010

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Heat Transfer in Intermediate Heat Exchanger Under Low Flow Rate Conditions

Hiroyasu Mochizuki

Nuclear Technology / Volume 170 / Number 1 / Pages 90-99

April 2010

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An Integral Effect Test on the Reflood Period of a Large-Break LOCA for the APR1400 Using ATLAS

Hyun Sik Park, Ki Yong Choi, Seok Cho, Kyoung Ho Kang, Nam Hyun Choi, Dong Jin Euh, Yeon Sik Kim, Won Pil Baek

Nuclear Technology / Volume 170 / Number 1 / Pages 100-113

April 2010

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Optimal Geometric Configuration for a Natural Circulation Loop

Jin Ho Song

Nuclear Technology / Volume 170 / Number 1 / Pages 114-122

April 2010

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Large Break Loss-of-Coolant Accident Analysis of VVER-1000 Reactor Using CATHARE Code

Luben Sabotinov, Abhishek Srivastava

Nuclear Technology / Volume 170 / Number 1 / Pages 123-132

April 2010

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Development of Advanced Loop-Type Fast Reactor in Japan

Shoji Kotake, Yoshihiko Sakamoto, Takatsugu Mihara, Shigenobu Kubo, Nariaki Uto, Yoshio Kamishima, Kazumi Aoto, Mikio Toda

Nuclear Technology / Volume 170 / Number 1 / Pages 133-147

April 2010

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System Design and Analysis of a 900-MW(thermal) Lead-Cooled Fast Reactor

Sang Ji Kim, Yonghee Kim, Sergi Hong, Chung Ho Cho, Jae-Hyuk Eoh, Jong Bum Kim, Myung Hwan Wi, Kwi Seok Ha, Eui Kwang Kim

Nuclear Technology / Volume 170 / Number 1 / Pages 148-158

April 2010

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Technological Feasibility of Two-Loop Cooling System in JSFR

Hidemasa Yamano, Shigenobu Kubo, Ken-Ichi Kurisaka, Yoshio Shimakawa, Hiromi Sago

Nuclear Technology / Volume 170 / Number 1 / Pages 159-169

April 2010

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Minor Actinide-Bearing Oxide Fuel Core Design Study for the JSFR

Masayuki Naganuma, Takashi Ogawa, Shigeo Ohki, Tomoyasu Mizuno, Shoji Kotake

Nuclear Technology / Volume 170 / Number 1 / Pages 170-180

April 2010

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Development of Passive Shutdown System for SFR

Shigeyuki Nakanishi, Takusaburo Hosoya, Shigenobu Kubo, Shoji Kotake, Misao Takamatsu, Takafumi Aoyama, Iwao Ikarimoto, Jungo Kato, Yoshio Shimakawa, Kiyoshi Harada

Nuclear Technology / Volume 170 / Number 1 / Pages 181-188

April 2010

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