Advanced transport codes for nuclear thermal rocket analysis
- Los Alamos National Lab., NM (United States)
Nuclear thermal rocket (NTR) propulsion systems will enable the manned exploration of our solar system. In the context of current and future safety standards and environmental constraints, the likelihood of any large nuclear engine testing program similar in scope to the ROVER/NERVA program is remote. Consequently, extensive computational verification of the safety, reliability, and performance of the reactor and spacecraft will be required. Fortunately, the development of new codes coupled with computer hardware advances will make this feasible and cost-effective. Although coupled-phenomena and separate-effects modeling at the component and system levels will be necessary, this paper addresses only radiation transport modeling of NTR systems and reviews the status and applicability of several codes that Los Alamos National Laboratory (LANL) is using.
- OSTI ID:
- 6672058
- Report Number(s):
- CONF-921102-; CODEN: TANSAO
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Vol. 66; Conference: Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future, Chicago, IL (United States), 15-20 Nov 1992; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
RADIATION TRANSPORT
COMPUTER CODES
CROSS SECTIONS
DISCRETE ORDINATE METHOD
MONTE CARLO METHOD
MULTIGROUP THEORY
PROPULSION SYSTEMS
ROCKETS
CALCULATION METHODS
NEUTRON TRANSPORT THEORY
TRANSPORT THEORY
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