Assessment of TRAC-PF1/MOD1 code for thermal-hydraulic behavior in pressure vessel during reflood in SCTF test with a radial power distribution

Main Author: Ohnuki, Akira
Corporate Author: Japan Atomic Energy Research Institute
Other Authors: Akimoto, Hajime, Murao, Yoshio
Published: Tokai-mura, Naka-gun, Ibaraki-ken: Japan Atomic Energy Research Institute, 1993.
Subjects:
LEADER 00935cam a2200253 7i4500
001 0000015343
005 20180316090000.0
005 20180316080154.0
008 180316 ja BI
040 |a NM 
090 0 0 |a M 93 139  
100 1 0 |a Ohnuki, Akira  
245 1 0 |a Assessment of TRAC-PF1/MOD1 code for thermal-hydraulic behavior in pressure vessel during reflood in SCTF test with a radial power distribution   |c Akira Ohnuki, Hajime Akimoto, Yoshio Murao. 
260 |a Tokai-mura, Naka-gun, Ibaraki-ken:   |b Japan Atomic Energy Research Institute,   |c 1993. 
300 |a viii, 85 p.;   |c 30 cm.. 
504 |a Includes bibliographical references 
650 0 4 |a Reactor safety  
650 0 4 |a Heat Transfer  
650 0 4 |a Void Fraction  
700 1 |a Akimoto, Hajime  
700 1 |a Murao, Yoshio  
710 2 |a Japan Atomic Energy Research Institute  
852 |a NM 
999 |a RP00018528  |b Book  |c JAERI - Open Shelf  |e HQ Library