The PBMR steady-state and coupled kinetics core thermal-hydraulics benchmark test problems

Reitsma, Frederik; Strydom, Gerhard; Haas, J.; Ivanov, Kostadin; Tyobeka, Bismark; Mphahlele, Ramatsemela; Downar, Thomas J.; Şeker, Volkan; Gougar, Hans D.; Cruz, D. F. Da; Sikik, U.E.

doi:10.1016/j.nucengdes.2005.12.007

Cited by 41 publications

(17 citation statements)

References 3 publications

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“…The maximum temperatures of the particulate debris predicted by MELCOR-H2 are higher than those predicted by Reitsma (2004), sometimes exceeding the predicted temperature values for a depressurized loss of forced convection without SCRAM by over 50 K. Reitsma's analysis showed that the maximum fuel temperature is about 1900 K. The MELCOR-H2 temperatures should be lower because the MELCOR-H2 analysis was for steady state conditions at full power. Further, the maximum allowable peak fuel temperature must be below 1600 °C to prevent TRISO fuel damage.…”

Section: Recommendations For Radial Fuel Temperature Calculationsmentioning

confidence: 81%

“…Rearranging the terms in Equation , one can approximate the temperature difference, ΔΤ, as shown in Equation (2)(3). (2)(3) The reference model that is used in this research is based on the 268 MWth power PBMR (Reitsma, 2004). The number of fuel pebbles in the core is estimated to be 330,000 pebbles (Nichols, 2001).…”

Section: Central Ring Near Bottommentioning

confidence: 99%

“…A plot of pebble bed thermal conductivity is shown in Figure 2-4 over a range of temperatures. In past calculations, the PBMR fuel bed thermal conductivity has been averaged to 20 W/(m K) (Reitsma, 2004). The average value seems reasonable given the reactor operation temperatures.…”

Section: Central Ring Near Bottommentioning

confidence: 99%

“…Solution of Equation (2)(3) results in a range of ΔT from 107.71 K to 53.81 K using k fuel equals 10 W/(m K) and 20 W/(m K) respectively. The power profile along the core varies compared to average normalized power from 0.0 to 1.39 (Reitsma, 2004). This variation in the axial power leads to a maximum fuel temperature difference ΔT =149.718K using k fuel equals 20 W/(m K) at the location of greatest power.…”

Section: Central Ring Near Bottommentioning

confidence: 99%

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Development of design and simulation model and safety study of large-scale hydrogen production using nuclear power.

Gelbard¹,

Rodríguez³

et al. 2007

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Before this LDRD research, no single tool could simulate a very high temperature reactor (VHTR) that is coupled to a secondary system and the sulfur iodine (SI) thermochemistry. Furthermore, the SI chemistry could only be modeled in steady state, typically via flow sheets. Additionally, the MELCOR nuclear reactor analysis code was suitable only for the modeling of light water reactors, not gas-cooled reactors. We extended MELCOR in order to address the above deficiencies. In particular, we developed three VHTR input models, added generalized, modular secondary system components, developed reactor point kinetics, included transient thermochemistry for the most important cycles [SI and the Westinghouse hybrid sulfur], and developed an interactive graphical user interface for full plant visualization. The new tool is called MELCOR-H2, and it allows users to maximize hydrogen and electrical production, as well as enhance overall plant safety. We conducted validation and verification studies on the key models, and showed that the MELCOR-H2 results typically compared to within less than 5% from experimental data, code-to-code comparisons, and/or analytical solutions.

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Section: Recommendations For Radial Fuel Temperature Calculationsmentioning

confidence: 81%

Section: Central Ring Near Bottommentioning

confidence: 99%

Section: Central Ring Near Bottommentioning

confidence: 99%

Section: Central Ring Near Bottommentioning

confidence: 99%

See 2 more Smart Citations

Development of design and simulation model and safety study of large-scale hydrogen production using nuclear power.

Gelbard¹,

Rodríguez³

et al. 2007

View full text Add to dashboard Cite

show abstract

“…Results of PBMR400 benchmark problems 7 are selected in order to demonstrate the neutronics and multiphysics capability of PRONGHORN. The problem is 2-D cylindrical geometry with a 2.925 m radius and a 14.5 m height.…”

Section: Pbmr400 Bench Mark Problemsmentioning

confidence: 99%

Progress on PRONGHORN Application to NGNP Related Problems

Knoll¹

2009

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Solving Nonlinear Systems Inside Implicit Time Integration Schemes for Unsteady Viscous Flows

Birken

2013

Notes on Numerical Fluid Mechanics and Multidisciplinary Design

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The PBMR steady-state and coupled kinetics core thermal-hydraulics benchmark test problems

Cited by 41 publications

References 3 publications

Development of design and simulation model and safety study of large-scale hydrogen production using nuclear power.

Development of design and simulation model and safety study of large-scale hydrogen production using nuclear power.

Progress on PRONGHORN Application to NGNP Related Problems

Solving Nonlinear Systems Inside Implicit Time Integration Schemes for Unsteady Viscous Flows

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