Volume 170; Issue 1

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Nuclear Technology
Volume 170; Issue 1

Nuclear Technology

Volume 170; Issue 1

1

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

Bang, In Cheol, Kim, Ji Hyun

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 1.08 MB

english, 2010

2

Development of Passive Shutdown System for SFR

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

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 809 KB

english, 2010

3

Development of Advanced Loop-Type Fast Reactor in Japan

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

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 1.96 MB

english, 2010

4

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

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

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 541 KB

english, 2010

5

Condensation Correlation for a Vertical Passive Condenser System

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

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 648 KB

english, 2010

6

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

Sabotinov, Luben, Srivastava, Abhishek

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 1.20 MB

english, 2010

7

The DEFOR-S Experimental Study of Debris Formation with Corium Simulant Materials

Kudinov, Pavel, Karbojian, Aram, Ma, Weimin, Dinh, Truc-Nam

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 1.18 MB

english, 2010

8

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

Kiss, Attila, Aszódi, Attila

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 1.33 MB

english, 2010

9

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

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

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 1.78 MB

english, 2010

10

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

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 200 KB

english, 2010

11

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

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

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 1.70 MB

english, 2010

12

Optimal Geometric Configuration for a Natural Circulation Loop

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 437 KB

english, 2010

13

European Experiments on 2-D Molten Core Concrete Interaction: HECLA and VULCANO

Journeau, Christophe, Bonnet, Jean Michel, Boccaccio, Eric, Piluso, Pascal, Monerris, Jose, Breton, Michel, Fritz, Gerald, Sevón, Tuomo, Pankakoski, Pekka H., Holmström, Stefan, Virta, Jouko

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 993 KB

english, 2010

14

Transient Conduction Heat Transfer Modeling in Concrete for the Simulation of Long-Term Phase of Molten Core-Concrete Interaction

Tourniaire, B., Spindler, B., Guillaumé, M.

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 452 KB

english, 2010

15

Interaction between Molten Corium UO 2+ X -ZrO 2 -FeO y and VVER Vessel Steel

Bechta, S. V., Granovsky, V. S., Khabensky, V. B., Krushinov, E. V., Vitol, S. A., Sulatsky, A. A., Gusarov, V. V., Almiashev, V. I., Lopukh, D. B., Bottomley, D., Fischer, M., Piluso, P., Miassoedov,

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 693 KB

english, 2010

16

Analysis and Justification of MAAP4.0.7 for PRA Level 1 Mission Success Criteria

Butler, Jennifer S., Kapitz, Darvin, Martin, Robert P., Seifaee, Farrokh, Sundaram, Ramu K.

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 993 KB

english, 2010

17

The Enhancements and Testing for the MCNPX 2.6.0 Depletion Capability

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

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 487 KB

english, 2010

18

An Assessment of Large-Eddy Simulation Toward Thermal Fatigue Prediction

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

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 972 KB

english, 2010

19

Heat Transfer in Intermediate Heat Exchanger under Low Flow Rate Conditions

Mochizuki, Hiroyasu

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 738 KB

english, 2010

20

Development of the Fission Product Release Analysis Code COPA-FPREL

Kim, Young Min, Cho, Moon Sung

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 913 KB

english, 2010

21

Technological Feasibility of Two-Loop Cooling System in JSFR

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

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 1.05 MB

english, 2010