Fast Reactors and Accelerator Driven Systems Knowledge Base
IAEA-TECDOC--1406: Primary Coolant Pipe Rupture Event in Liquid Metal Cooled Reactors
Proceedings of a technical meeting held in Kalpakkam, India 13-17 January 2003
International Atomic Energy Agency, Vienna (Austria), IAEA-TECDOC--1406
Abstract
Thruough Nuclear Energy Department's Technical Working Group on Fast Reactors (TWG-FR), IAEA provides a forum for exchange of information on national programmes, collaborative assessments, knowledge preservation and cooperative research in areas agreed by the Member States with fast reactor and partitioning and transmutation development programmes. Trends in innovative fast reactor and ADS designs and technology development are periodically summarized in status report and rupture of the primary coolant pipe in a liquid metal cooled fast reactor (both critical and sub-critical) is a topic of major concern for the design of such reactors.
view the full text of this conference report (format: PDF, size= 3849kB, 152 pages)
see also:
- Covers and foreword (4 pages, format: PDF, size= 173kB )
- Summary (15 pages, format: PDF, size= 190kB )
- Index of contents (2 pages, format: PDF, size= 102kB )
- Abbreviations (3 pages, format: PDF, size= 69kB )
- Participants (3 pages, format: PDF, size= 31kB )
Articles
Safety philosophy of primary pipe rupture event in prototype fast breeder reactor
Bhkoje, S.B. (Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam (India))
Philosophy of leak before break assessment for Japanese prototype FBR
Wakai, T.; Aoto, K.; Ichimiya, M. (Japan Nuclear Cycle Development Institute (JNC), O-arai Engineering Center, Ibaraki (Japan)); Ito, K. (Japan Nuclear Cycle Development Institute (JNC), Monju Construction Office, Ibaraki (Japan))
Main pipe rupture accident analysis for the Chinese experimental fast reactor
Yang Hongyi; Xu Mi (China Institute of Atomic Energy (CIAE), Beijing (China))
Rupture of LIPOSO in Superphenix
Dufour, P.; Louvet, J.; Lo Pinto, P. (CEA DEN/Cadarache, St. Paul-lez-Durance (France))
Theoretical and experimental assessment of structural integrity of primary pipe
Chellapandi, P.; Biswas, A.; Chetal, S.C.; Bhoje, S.B. (Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam (India))
A simplified crack growth assessment procedure for PCP in FBR
Wakai, T.; Aoto, K. (Japan Nuclear Cycle Development Institute (JNC), O-arai Engineering Center, Ibaraki (Japan))
Thermal hydraulic consequences of primary pipe rupture
Kasinathan, N.; Natesan, K.; Selvaraj, P.; Chelapandi, P.; Chetal, S.C. (Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam (India))
Analysis of primary pipe break for the Korean advanced liquid metal reactor (KALIMER)
Jeong, H.Y.; Chang, W.P.; Lee, Y.B.; Hahn, D. (Korea Atomic Energy Research Institute (KAERI), Daejon (Korea, Republic of))
Analysis of emergency situations caused by BN-800 primary circuit pressure pipe depressurization
Gorbunov, V.S.; Zamiatin, V.A.; Kamanin, Yu.L.; Kuzavkov, N.G.; Sobolev, V.A. (Experimental Designing Bureau of Machine Building (OKBM), Nizhny Novgorod (Russian Federation))
Improved primary pipe design concepts for future FBR
Chetal, S.C.; Chellapandi, P. (Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam (India))