Published January 30, 2007 | Version v1
Journal article

Hot Hydrogen Test Facility

  • 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

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