| LDR | | 00000nmm u2200205 4500 |
| 001 | | 000000334374 |
| 005 | | 20250204100036 |
| 008 | | 181129s2016 ||| | | | eng d |
| 020 | |
▼a 9780438309661 |
| 035 | |
▼a (MiAaPQ)AAI10970724 |
| 035 | |
▼a (MiAaPQ)OhioLINK:osu1468426881 |
| 040 | |
▼a MiAaPQ
▼c MiAaPQ
▼d 248032 |
| 049 | 1 |
▼f DP |
| 082 | 0 |
▼a 539.76 |
| 100 | 1 |
▼a Eades, Michael J. |
| 245 | 10 |
▼a 135Xe in LEU Cermet Nuclear Thermal Propulsion Systems. |
| 260 | |
▼a [S.l.] :
▼b The Ohio State University.,
▼c 2016 |
| 260 | 1 |
▼a Ann Arbor :
▼b ProQuest Dissertations & Theses,
▼c 2016 |
| 300 | |
▼a 150 p. |
| 500 | |
▼a Source: Dissertation Abstracts International, Volume: 80-01(E), Section: B. |
| 500 | |
▼a Adviser: Blue Thomas. |
| 502 | 1 |
▼a Thesis (Ph.D.)--The Ohio State University, 2016. |
| 520 | |
▼a Nuclear Thermal Propulsion (NTP) is currently a topic of research for NASA. NASA has the goal of sending humans to Mars and Nuclear Thermal Propulsion (NTP) is an appealing technology to aid in this endeavor. In the simplest terms, an NTP system |
| 520 | |
▼a The overarching goal of this work is to better understand NTP technology so that it may one day help with a human Mars mission. This work focuses on a subset of NTP systems that use a combination of LEU and tungsten cermet fuel and addresses the |
| 520 | |
▼a In this work, two LEU cermet NTP point designs are presented and used as reference systems for the study of 135Xe in LEU cermet NTP systems. These point designs were produced with a thorough search of the rocket performance design space. |
| 520 | |
▼a Using infinite lattice burnup calculations, it was found that MCNP 6.1.1 Beta and Serpent 2 produced very similar results and that burnup cells across the fuel element were not needed to capture spatial self shielding effects. The infinite latti |
| 520 | |
▼a The possible effect of 135mXe on xenon worth in LEU cermet NTP systems was found by using the model based TENDL-2014 nuclear data library and Serpent 2. Model based TENDL cross sections were used because no experimentally determined cross sectio |
| 520 | |
▼a A relationship to estimate the performance (in terms of Isp loss) as a function of control drum angle is derived and presented. Mitigation strategies are identified that show promise for counteracting the effects of 135Xe and maximizing the per |
| 520 | |
▼a It is recommended for future work that an integrated reactor systems code be developed to examine 135Xe in LEU cermet NTP more thoroughly. In addition, this work has identified a need for basic nuclear data experiments to measure the cross secti |
| 590 | |
▼a School code: 0168. |
| 650 | 4 |
▼a Nuclear engineering. |
| 690 | |
▼a 0552 |
| 710 | 20 |
▼a The Ohio State University.
▼b Nuclear Engineering. |
| 773 | 0 |
▼t Dissertation Abstracts International
▼g 80-01B(E). |
| 773 | |
▼t Dissertation Abstract International |
| 790 | |
▼a 0168 |
| 791 | |
▼a Ph.D. |
| 792 | |
▼a 2016 |
| 793 | |
▼a English |
| 856 | 40 |
▼u http://www.riss.kr/pdu/ddodLink.do?id=T15001333
▼n KERIS |
| 980 | |
▼a 201812
▼f 2019 |
| 990 | |
▼a 관리자
▼b 정현우 |