Published 1999 | Version v1
Journal article

Thermal shock analysis of the BNL/AGS mercury target experiments

  • 1. Oak Ridge National Lab., TN (United States)

Description

The Spallation Neutron Source is a 1-MW accelerator-based pulsed neutron source facility being designed by several national laboratories and led by Oak Ridge National Laboratory. Liquid mercury will be used as the target material. Several important issues must be resolved to ensure the feasibility of mercury as a target material. One of the key issues is related to the thermal shock loads caused by rapid energy deposition of the proton beam to the mercury target. The rate of temperature rise is enormous (∼107 C/s) during the very brief beam pulse (∼0.5 micros). The pressure waves will interact with the target structure walls and the bulk flow field. Understanding and predicting propagation of pressure pulses are critical for establishing the feasibility of construction and safe operation of the facility. To resolve such issues, a benchmarking database needs to be developed to validate computational models calculating the pressure wave behavior in the mercury target. Collaboration was initiated to conduct experiments wit h a close- to full-scale cylindrical vessel filled with mercury. Specific experiments were conducted at the Brookhaven National Laboratory's Alternating Gradient Synchrotron (AGS) in June of 1997. In these experiments, a high-energy (24-GeV) proton beam deposited ∼61% of its energy in the mercury target over a time period of ∼0.1 micros. Several optical strain gauges were attached to the surface of the steel target wall. The proton pulse shape was roughly parabolic and was estimated to be of ∼0.05 m in radius. Computational models were developed and validated against the AGS data. The ANSYS/Multiphysics code system modeled the test target in Ref. 3, using acoustic elements for mercury fluid and solid elements for the target wall. The authors discuss a two-dimensional model of the ANSYS/Multiphysics code for the same test target. In this effort, solid elements were used to model the liquid mercury without allowing shear between these mercury elements. The ANSYS code uses the implicit Newmark time integration method, coupled with Newton-Raphson solution techniques to obtain the time histories. Materials were assumed to be homogeneous and isotropic, and viscous dissipation was neglected in the calculations. Figure 1 shows a comparison between the calculation and the data. Also, a comparison against the CTH results is included in the same figure

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
80
Journal Page Range
p. 312-313
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
1999 annual meeting of the American Nuclear Society (ANS)
Dates
6-10 Jun 1999
Place
Boston, MA (United States)

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
30057280
Subject category
S43: PARTICLE ACCELERATORS; S07: ISOTOPES AND RADIATION SOURCES;
Resource subtype / Literary indicator
Conference
Descriptors DEI
A CODES; ACCELERATOR FACILITIES; BENCHMARKS; ENERGY DEPOSITION; LIQUID METALS; MATHEMATICAL MODELS; MERCURY; NEUTRON SOURCES; TARGETS; THERMAL SHOCK; VALIDATION
Descriptors DEC
COMPUTER CODES; ELEMENTS; FLUIDS; LIQUIDS; METALS; PARTICLE SOURCES; RADIATION SOURCES; TESTING

Optional Information

Secondary number(s)
CONF-990605--