Hot Hydrogen Test Facility
Creators
- 1. Idaho National Laboratory, PO Box 1625, Idaho Falls, ID 83415 (United States)
Description
The core in a nuclear thermal rocket will operate at high temperatures and in hydrogen. One of the important parameters in evaluating the performance of a nuclear thermal rocket is specific impulse, ISP. This quantity is proportional to the square root of the propellant's absolute temperature and inversely proportional to square root of its molecular weight. Therefore, high temperature hydrogen is a favored propellant of nuclear thermal rocket designers. Previous work has shown that one of the life-limiting phenomena for thermal rocket nuclear cores is mass loss of fuel to flowing hydrogen at high temperatures. The hot hydrogen test facility located at the Idaho National Lab (INL) is designed to test suitability of different core materials in 2500 deg. C hydrogen flowing at 1500 liters per minute. The facility is intended to test low activity uranium containing materials but is also suited for testing cladding and coating materials. In this first installment the facility is described. Automated data acquisition, flow and temperature control, vessel compatibility with various core geometries and overall capabilities are discussed
Additional details
Identifiers
- DOI
- 10.1063/1.2437477;
Publishing Information
- Journal Title
- AIP Conference Proceedings
- Journal Volume
- 880
- Journal Issue
- 1
- Journal Page Range
- p. 380-388
- ISSN
- 0094-243X
- CODEN
- APCPCS
Conference
- Title
- 11. conference on thermophysics applications in microgravity; 24. symposium on space nuclear power and propulsion; 5. conference on human/robotic technology and the vision for space exploration; 5. symposium on space colonization; 4. symposium on new frontiers and future concepts
- Acronym
- International forum-STAIF 2007
- Dates
- 11-15 Feb 2007
- Place
- Albuquerque, NM (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39071547
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DATA ACQUISITION; EVALUATION; FISSION; HYDROGEN; MOLECULAR WEIGHT; NUCLEAR FUELS; PERFORMANCE; PROPULSION; PROPULSION REACTORS; PULSES; REACTOR FUELING; ROCKETS; TEMPERATURE CONTROL; TEST FACILITIES; TESTING; URANIUM
- Descriptors DEC
- ACTINIDES; CONTROL; ELEMENTS; ENERGY SOURCES; FUELS; MATERIALS; METALS; NONMETALS; NUCLEAR REACTIONS; POWER REACTORS; REACTOR MATERIALS; REACTORS
Optional Information
- Notes
- (c) 2007 American Institute of Physics