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Title: Benchmark of the Kilowatt Reactor Using Stirling TechnologY (KRUSTY) Component Critical Configurations

Journal Article · · Nuclear Technology
ORCiD logo [1];  [2];  [2];  [2];  [2];  [2];  [2]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Texas A & M Univ., College Station, TX (United States)
  2. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

Kilowatt Reactor Using Stirling TechnologY (KRUSTY) was a prototype for the U.S. National Aeronautics and Space Administration’s Kilopower Program. KRUSTY has a highly enriched uranium–molybdenum alloy (with 7.65 wt% molybdenum) annular core reflected by beryllium oxide with an outer stainless steel shield. Five configurations from the experimental campaign were chosen to be evaluated as benchmark cases. Uncertainties were evaluated in five categories: (1) criticality measurement, (2) mass and density, (3) dimensions, (4) material compositions, and (5) positioning. The largest contribution to the overall uncertainty in each case was from the radial alignment of the movable platen. A simplified model was created to increase computational efficiency, and an average bias of –16 pcm was calculated due to the simplifications. Sample calculations were completed for each case using MCNP6.2, COG, and MC21, all with ENDF/B-VIII.0 nuclear data. For MCNP6.2, the average difference (absolute value) between the calculated and experimental $$k_{eff}$$ for the five configurations was 14 pcm for both the detailed and the simplified models. The $$k_{eff}$$ results from all three codes are within 1σ of the benchmark values. KRUSTY’s value as a benchmark is due to its sensitivity to beryllium and molybdenum. For beryllium, KRUSTY adds an 18th benchmark with a total cross-section sensitivity greater than 0.05%/%/(unit lethargy). For molybdenum, KRUSTY adds a 9th benchmark with a total cross-section sensitivity greater than 0.004%/%/(unit lethargy).

Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
Grant/Contract Number:
89233218CNA000001
OSTI ID:
1900405
Journal Information:
Nuclear Technology, Vol. 208, Issue 4; ISSN 0029-5450
Publisher:
Taylor & Francis - formerly American Nuclear Society (ANS)Copyright Statement
Country of Publication:
United States
Language:
English

References (10)

Kilowatt Reactor Using Stirling TechnologY (KRUSTY) Cold Critical Measurements journal June 2020
ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data journal February 2018
Compendium of Material Composition Data for Radiation Transport Modeling report March 2011
Results of the KRUSTY Warm Critical Experiments journal June 2020
Small modular reactors: Simpler, safer, cheaper? journal September 2012
Kilowatt Reactor Using Stirling TechnologY (KRUSTY) Component-Critical Experiments journal June 2020
MC21 v.6.0 – A continuous-energy Monte Carlo particle transport code with integrated reactor feedback capabilities journal August 2015
Kilopower Project: The KRUSTY Fission Power Experiment and Potential Missions journal June 2020
Results of the KRUSTY Nuclear System Test journal June 2020
Adjoint-Based Sensitivity and Uncertainty Analysis for Density and Composition: A User’s Guide journal March 2017

Figures / Tables (25)