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Dr. Jose G. Lepervanche on the 70th Anniversary of the Hiroshima Bombing (English). Video link: https://youtu.be/vLT-TOY0mOQ
Dr. Jose G. Lepervanche on the 70th Anniversary of the Hiroshima Bombing (Spanish) Video link: https://youtu.be/gCO-_QVZ_7Y
Nuclear Research Reactor RV-1 Venezuela. Pictures to support lecture about nuclear energy.
#UnderPrague. We took this tour to learn more about the Cold War times, to visit one of nuclear bunkers in Prague and to see their big collection of insignias, newspapers, magazines, pictures, uniforms, and gas masks. Thanks to Katerine for her detailed explanations. I wish we had more time to see the exhibits with more detail. Under Prague. Nuclear bunker for 5000 people. #nuclearbunkertour #nuclearbunkerprague #exploringprague #praguejnderground — in Prague, Czech Republic. “Peace Lessons Under Prague: Exploring a Nuclear Bunker” coming soon to #DrJoseCampus. See our pictures in Dr. Lepervanche Global Learning. See all photos here https://flic.kr/s/aHskCaC1bK We also visited the Museum of Communism in Prague.
Primary SubjectSPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS (E3100)
SourceInternational Atomic Energy Agency, Vienna (Austria); Proceedings series; 599 p; ISBN 92-0-020381-7; 
; 1981; v. 3 p. 277-292; IAEA; Vienna; International conference on current nuclear power plant safety issues; Stockholm, Sweden; 20 – 24 Oct 1980; IAEA-CN–39/212
Record TypeBook
Country of publication International Atomic Energy Agency (IAEA)
Descriptors (DEI) BWR TYPE REACTORS, CONTAINMENT, CONTROL SYSTEMS, FAILURES, HYDROGEN, PROBABILITY, REACTOR ACCIDENTS, REACTOR SAFETY, REACTOR SHUTDOWN, SYSTEM FAILURE ANALYSIS
Descriptors (DEC) ACCIDENTS, ELEMENTS, NONMETALS, REACTORS, SAFETY, SYSTEMS ANALYSIS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference Number 13680596
Publication Year 1981
INIS Volume 13
INIS Issue 13
Hydrogen control is important in post-accident situations because of possibilities for containment rupture due to hydrogen deflagration or detonation. Post-accident hydrogen generation in BWR containments is analyzed as a function of engineered hydrogen control system, assumed either nitrogen inerting or air dilution. Fault tree analysis was applied to assess the failure probability per demand of each system. These failure rates were then combined with the probability of accidents producing various hydrogen generation rates to calculate the overall system hydrogen control probability. Results indicate that both systems render approximately the same overall hydrogen control failure rate (air dilution: 8.3 x 10-2; nitrogen inerting: 1.3 x 10-2-2 x 10-3). Drywell entries and unscheduled shutdowns were also analyzed to determine the impact on the total BWR accident risk as it relates to the decay heat removal system. Results indicate that inerting may increase the overall risk due to a possible increase in the number of unscheduled shutdowns due to a lessened operator ability to correct and identify unidentified leakage from the primary coolant system. Further, possible benefits of inerting due to reduced torus corrosion and fire risk in containment appear to be dominated by the possible operation-related disadvantages. (orig.)
Primary Subject ENVIRONMENTAL SCIENCES (C5200)
Record Type Journal article
Journal Nuclear Engineering and Design; ISSN 0029-5493; ; v. 64(3); p. 329-346
Country of publication Netherlands
Descriptors (DEI) BWR TYPE REACTORS, CONTAINMENT, CONTROL SYSTEMS, DESIGN BASIS ACCIDENTS, FAILURES, FAULT TREE ANALYSIS, HYDROGEN, LAW, PROBABILITY, REACTOR SAFETY, REGULATIONS
Descriptors (DEC) ACCIDENTS, ELEMENTS, NONMETALS, REACTOR ACCIDENTS, REACTORS, SAFETY, SYSTEM FAILURE ANALYSIS, SYSTEMS ANALYSIS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference Number 12629521
Publication Year 1981
INIS Volume 12
INIS Issue 20
Here is another example about the importance of accurate data. When I was the world’s youngest manager of a nuclear research reactor we had a old control room with paper displays that generated graphics based on data received from sensors located at the bottom of the reactor core. Every year we had to remove the fuel from the reactor pool, store them in a safe pool, remove water of reactor pool, and plan to go down properly protected to replace the sensors,. We practice in a simulation room to replaced them in less than two minutes. The day of the real change, we went according to radioactive protocol depending of amount of radioactive exposure we had before. I had to go to set the example. It was important to receive accurate data that was going to be registered in an old control room . Here are some pictures of those days. Please share a similar case in your industry or workplace.
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