Predictive methods for assessing corrosion damage to BWR piping and PWR steam generators.

Saved in:
Bibliographic Details
Main Author: Okada, Hideya (ed.)
Corporate Author: U.S.-Japan Joint Symposium on Light Water Reactor
Other Authors: Staehle, Roger (ed.)
Format: Conference Proceeding Book
Language:English
Published: Houston : National Association of Corrosion Engineers, c1982.
Subjects:
Tags: Add Tag
No Tags, Be the first to tag this record!

MARC

LEADER 00000nam a2200000 a 4500
008 170703t1982####xxua|||f#|||||10| 0#eng#d
003 AR-SmCIES
041 7 |a en   |2 ISO 639-1 
080 |a 621.039.524.4 
091 |a 50135 
100 1 |a Okada, Hideya  |e ed. 
245 1 0 |a Predictive methods for assessing corrosion damage to BWR piping and PWR steam generators. 
260 |a Houston :  |b National Association of Corrosion Engineers,  |c c1982. 
300 |a xxix, 393, 6 p. :  |b il., tablas 
500 |a Proceeding of 1978 the First U.S.-Japan Joint Symposium on Light Water Reactor. Ver p. xvii. 
500 |a Bibliografía al final de cada artículo 
591 |a Prestado a Chocrón, Mauricio 20/10/2014 
591 |a El nombre de la reunión se tomó del reg. de la LC 
650 7 |a REACTORES REFRIGERADOS POR AGUA  |2 INIS 
650 7 |a REACTORES DE AGUA EN EBULLICION(BWR)  |2 INIS 
650 7 |a REACTORES TIPO PWR  |2 INIS 
650 7 |a CORROSION  |2 INIS 
650 7 |a TUBERIAS  |2 INIS 
650 7 |a REUNIONES  |2 INIS 
700 1 |a Staehle, Roger  |e ed. 
711 2 |a U.S.-Japan Joint Symposium on Light Water Reactor  |n 1  |c Fuji Institute of Education and Training,JP  |d 1978 
999 |c 25193  |d 25193