Vertical rod temperatures
An important factor affecting the decision on the use of a seal around the VSR on ``C`` is the temperature at which the rod can be expected to reach. Also the temperature of the rod-tip affects the choice of tip moderating material. These temperatures are calculated for a given set of conditions for ``C`` pile. The results of the calculations are best seen by referring to the attached figures. The affects of emissivity and weight of rod can be estimated by comparing the proper curves. The assumed conditions for calculating each curve are important and therefore, the basis for each curve is given separately.
- Research Organization:
- Hanford Site (HNF), Richland, WA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 10121266
- Report Number(s):
- HDC-2296; ON: DE95007516; TRN: AHC29509%%173
- Resource Relation:
- Other Information: DN: Declassified; PBD: 14 Aug 1951
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HANFORD PRODUCTION REACTORS
SCRAM RODS
TEMPERATURE DEPENDENCE
MODERATORS
THERMAL CONDUCTIVITY
HISTORICAL ASPECTS
CALCULATION METHODS
TEMPERATURE GRADIENTS
220400
220600
210300
CONTROL SYSTEMS
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
POWER REACTORS
NONBREEDING
GRAPHITE MODERATED
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HANFORD PRODUCTION REACTORS
SCRAM RODS
TEMPERATURE DEPENDENCE
MODERATORS
THERMAL CONDUCTIVITY
HISTORICAL ASPECTS
CALCULATION METHODS
TEMPERATURE GRADIENTS
220400
220600
210300
CONTROL SYSTEMS
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
POWER REACTORS
NONBREEDING
GRAPHITE MODERATED