Performance of a clad tungsten rod spallation neutron source target

被引:7
作者
Sommer, WF [1 ]
Maloy, SA
Louthan, MR
Willcutt, GJ
Ferguson, PD
James, MR
机构
[1] Los Alamos Natl Lab, Los Alamos, NM USA
[2] Westinghouse Savannah River Co, Savannah River Natl Lab, Aiken, SC 29808 USA
[3] Oak Ridge Natl Lab, Oak Ridge, TN USA
关键词
tungsten; neutron source; irradiation;
D O I
10.13182/NT05-A3653
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Tungsten rods, slip-clad with Type 304L stainless steel, performed successfully as a spallation neutron source target operating to a peak fluence of similar to 4 X 10(21) p/cm(2). The target was used as a neutron source during the Accelerator Production of Tritium (APT) materials irradiation program at the Los Alamos Neutron Science Center. Tungsten rods of 2.642-mm diameter were slip-fit in Type 304L stainless steel tubes that had an inner diameter of 2.667 mm. The radial gap was filled with helium at atmospheric pressure and room temperature. Los Alamos High Energy Transport (LAHET) calculations suggest a time-averaged peak power deposition in the W of 2.25 kW/cm(3). Thermal-hydraulic calculations indicate that the peak centerline W temperature reached 271 degrees C. The LAHET calculations were also used to predict neutron and proton fluxes and spectra for the complex geometry used in the irradiation program. Activation foil sets distributed throughout the experiment were used to determine target neutronics performance as a comparison to the LAHET calculations. Examination of the irradiated target assemblies revealed no significant surface degradation or corrosion on either the Type 304L or the W surfaces. However, it was clear that the irradiation changed material properties because post-proton-irradiation measurements on Type 304L test samples from the APT program demonstrated increases in the yield strength and decreases in the ductility and fracture toughness with increasing dose, and the wrought W rod samples became brittle. Fortunately, the slip-clad target design subjects the materials to very low stress.
引用
收藏
页码:303 / 313
页数:11
相关论文
共 24 条
  • [1] CLAYTON JC, 1993, PROCEEDINGS OF THE SIXTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, P457
  • [2] FOSTER AR, 1997, BASIC NUCL ENG, P76
  • [3] Garzarolli F, 1997, PROCEEDINGS OF THE EIGHTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOLS 1 AND 2, P977
  • [4] GODESAR R, 1973, P INT C PHYS MET REA, P308
  • [5] HAYNS MR, 1973, P INT C PHYS MET REA, P331
  • [6] HUGHES HG, 1998, P 2 INT TOP M NUCL A, P281
  • [7] Spectral unfolding of mixed proton/neutron fluences in the LANSCE irradiation environment
    James, MR
    Maloy, SA
    Sommer, WF
    Ferguson, PD
    Fowler, MM
    Mueller, GE
    Corzine, RK
    [J]. REACTOR DOSIMETRY: RADIATION METROLOGY AND ASSESSMENT, 2001, 1398 : 167 - 174
  • [8] LILLARD S, 1996, COMMUNICATION
  • [9] *LOS AL NAT LAB, 1998, SPTMP9744 LOS AL NAT
  • [10] *LOS AL NAT LAB, 1998, APT1021998109 LOS AL