Published November 1989
| Version v1
Journal article
Evaluation of heat pipes for decay heat removal
Description
This paper summarizes the results of a study to evaluate the feasibility of using heat pipes for decay heat removal in an advanced liquid-metal-cooled reactor. Rockwell International's 450-MW(electric) pool-type sodium advanced fast reactor (SAFR) was used as a basis for this evaluation. The results, however, are generally applicable to other liquid-metal reactor designs. Several combinations of heat pipes and heat pipes with other decay heat removal systems were studied. Heat pipe evaluation is discussed with respect to thermal-hydraulic analysis, safety evaluation, and cost estimate
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 60
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 732-733
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
- Dates
- 26-30 Nov 1989.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22085793
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; CESIUM; FAILURES; HEAT PIPES; HEAT TRANSFER; HYDRAULICS; LIQUID METAL COOLED REACTORS; MERCURY; PERFORMANCE; POTASSIUM; REACTOR COOLING SYSTEMS; SODIUM; SPECIFICATIONS
- Descriptors DEC
- ALKALI METALS; COOLING SYSTEMS; ELEMENTS; ENERGY TRANSFER; METALS; REACTOR COMPONENTS; REACTORS; REMOVAL
Optional Information
- Secondary number(s)
- CONF-891103--.