Published 1992
| Version v1
Journal article
Computational neutronic analysis of the nuclear vapor thermal rocket engine
- 1. Univ. of Florida, Gainesville (United States)
Description
Calculational procedures and results are presented for the neutronic analysis of the Nuclear Vapor Thermal Reactor (NVTR) rocket engine. The NVTR, in a rocket engine, uses modified NERVA geometry and systems with the solid fuel replaced by highly enriched (>85%) uranium tetrafluoride (UF4) vapor. In the NVTR, the hydrogen propellant is the primary coolant, is physically separated from the UF4 vapor (which is not circulated), is maintained at high pressure (50 to 100 atm), and exits the core at 3100 to 3500 K
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 66
- Journal Page Range
- p. 252-253.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- past, present, and future.
- Acronym
- Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction
- Dates
- 15-20 Nov 1992.
- Place
- Chicago, IL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24051012
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DISCRETE ORDINATE METHOD; HYDROGEN FUELS; MULTIGROUP THEORY; NEUTRON TRANSPORT THEORY; NUMERICAL SOLUTION; PROPULSION; PROPULSION REACTORS; REACTOR KINETICS; ROCKETS; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS; X CODES
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; FUELS; KINETICS; POWER REACTORS; REACTORS; SYNTHETIC FUELS; TRANSPORT THEORY
Optional Information
- Secondary number(s)
- CONF-921102--.