RSMASS-D: Reactor and Shield Mass Minimization Models
- Sandia National Lab. (SNL-CA), Livermore, CA (United States)
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Three relatively simple mathematical models have been developed to estimate minimum reactor and radiation shield masses for liquid metal cooled reactors (LMR's), in-core thermionic reactors (TI's) and out-of-core thermionic reactors (OTR's). The approach was based on much of the methodology developed for the RSMASS model (Marshall 1986). The models use a combination of simple equations derived from reactor physics and other fundamental considerations along with tabulations of data from more detailed neutron and gamma transport theory computations. All three models vary basic design parameters within an allowed range to achieve a parameter choice which yields a minimum mass for the power level and operational time of interest. The impact of critical mass, fuel damage and thermal limitations are accounted for in the computations. Thermionic requirements are also accounted for in the thermionic reactor models. All major reactor component masses are estimated as well as instrumentation and control (I C), boom and safety system mass. A new shield model was developed and incorporated into all three models. The new shield model is more accurate and simpler to use than the approach used in the original +. The estimated reactor and shield masses agree with the mass predictions from detailed calculations within 16 percent for all three models.
- Research Organization:
- Sandia National Lab. (SNL-CA), Livermore, CA (United States); Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5504216
- Report Number(s):
- CONF-910116-; CODEN: APCPC; TRN: 91-021917
- Journal Information:
- AIP Conference Proceedings, Vol. 217, Issue 1; Conference: 8. Symposium on Space Nuclear Power Systems, Albuquerque, NM (United States), 6-10 Jan 1991; ISSN 0094-243X
- Publisher:
- American Institute of Physics (AIP)
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
LIQUID METAL COOLED REACTORS
DESIGN
THERMIONIC REACTORS
CRITICALITY
MATHEMATICAL MODELS
NEUTRON FLUX
REACTOR CORES
SHIELDING
SPACE POWER REACTORS
MOBILE REACTORS
POWER REACTORS
RADIATION FLUX
REACTOR COMPONENTS
REACTORS
Nuclear Criticality Safety Program (NCSP)
NESDPS Office of Nuclear Energy Space and Defense Power Systems
Minimum Reactor and Radiation Shield Masse
Reactor/Shield Mass Model (RSMASS)
Liquid Metal Cooled Reactor (LMR)
In-Core Thermionic Reactors (TI)
210600* - Power Reactors
Auxiliary
Mobile Package
& Transportable