Advanced transport codes for nuclear thermal rocket analysis

Conference · Wed Jan 01 04:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6672058

Perry, R T; Buksa, J J; Houts, M G ^[1]

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1. 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--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 66
• Country of Publication: United States
• Language: English

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