RSMASS-D: Reactor and Shield Mass Minimization Models

Conference · Thu Jan 10 04:00:00 EST 1991 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.40044· OSTI ID:5504216

Marshall, A. C. ^[1]; Gallup, D. R. ^[2]

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1. Sandia National Lab. (SNL-CA), Livermore, CA (United States)
2. 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--
• Conference Information: Journal Name: AIP Conference Proceedings Journal Issue: 1 Journal Volume: 217
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210600* -- Power Reactors
Auxiliary
Mobile Package
& Transportable
CRITICALITY
DESIGN
In-Core Thermionic Reactors (TI)
LIQUID METAL COOLED REACTORS
Liquid Metal Cooled Reactor (LMR)
MATHEMATICAL MODELS
MOBILE REACTORS
Minimum Reactor and Radiation Shield Masse
NESDPS Office of Nuclear Energy Space and Defense Power Systems
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
POWER REACTORS
RADIATION FLUX
REACTOR COMPONENTS
REACTOR CORES
REACTORS
Reactor/Shield Mass Model (RSMASS)
SHIELDING
SPACE POWER REACTORS
THERMIONIC REACTORS