The Nukiyama curve
Creators
Description
Shortly after the late Professor Shiro Nukiyama was notified that he was the recipient of the 1968 Max Jakob Award, a collection of his research papers was reprinted in a bound volume and published. The preface for this volume was written by Professor Yasushi Tanasawa who was Professor Nukiyama's co-worker at Tohoku University. The preface of this paper carries an interesting account of how this historic experiment was conducted. It also describes how the investigator himself came to learn, many years later, the extent of attention that his experiment had won abroad. It was learned, however, a considerable time after a meeting, that an extensive study on boiling heat transfer was being conducted in the USA because the cooling performance of a boiling water type nuclear reactor was restricted at the point of maximum boiling rate, but that a complete solution had not been obtained. On reflection, some experiments on the point of maximum boiling rate from 1929 to 1933 were made
Additional details
Additional titles
- Subtitle (English)
- It's impact on heat transfer science and engineering
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0612-X
- Imprint Title
- Proceedings of the ASME-JSME thermal engineering joint conference, 1991
- Imprint Pagination
- 528 p.
- Journal Page Range
- p. 437-440.
Conference
- Title
- 3. American Society of Mechanical Engineers/Japan Society of Mechanical Engineers (ASME/JSME) thermal engineering conference.
- Dates
- 17-22 Mar 1991.
- Place
- Reno, NV (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23036236
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOILING DETECTION; BUBBLE GROWTH; BWR TYPE REACTORS; HEAT TRANSFER; HISTORICAL ASPECTS; PERFORMANCE TESTING; REACTOR COOLING SYSTEMS; REACTOR SAFETY EXPERIMENTS; STEAM
- Descriptors DEC
- COOLING SYSTEMS; DETECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-910375--.