Study of clad ballooning and rupture behaviour of Indian PHWR fuel pins under transient heating condition in steam environment-Reference-Cited by-同舟云学术

Study of clad ballooning and rupture behaviour of Indian PHWR fuel pins under transient heating condition in steam environment

Published:2017-11 Issue: Volume:495 Page:332-342
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Sawarn Tapan K.,Banerjee Suparna,Sheelvantra Smita S.,Singh J.L.,Bhasin Vivek

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference21 articles.

1. A. K. Babar, R. K. Saraf, A. Kakodkar, reportProbabilistic Safety Assessment of Narora Atomic Power Project. BARC Report 1445, 1989.

2. Experiments on Ballooning in Pressurized and Transiently Heated Zircaloy-4 Tube;Markiewicz,1988

3. Measurement of Fission Gas Release from Irradiated Nuclear Fuel Elements;Viswanathan,2005

4. Deformation and Rupture Behavior of Zircaloy Cladding under Simulated Loss of coolant Accident Conditions, Zirconium in the Nuclear Industry;Chung,1977

5. Studies on Zircaloy Fuel Clad Ballooning in a Loss of coolant Accident—results of Burst Tests with Indirectly Heated Fuel Rod Simulators, Zirconium in the Nuclear Industry (Fourth Conference);Erbacher,1979

Cited by 13 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Zircaloy-4 fuel pin failure under simulated loss-of-coolant-accident conditions: Creep and rupture;Nuclear Engineering and Design;2024-11

2. New burst criteria for loss of coolant accidents radiological consequences assessment;Annals of Nuclear Energy;2024-10

3. Forecasting of Nuclear Power Plant Burst Factors using Radial Basis Neural Network throughout Loss of Coolant Accident;2024 3rd International Conference on Advancement in Electrical and Electronic Engineering (ICAEEE);2024-04-25

4. Determination of critical material damage parameter for Indian clad tube burst behavior under severe accident scenario;Procedia Structural Integrity;2024

5. Model for determining rupture area in Zircaloy cladding under LOCA conditions;Nuclear Engineering and Design;2023-01