Recommended design correlations for S-65 beryllium

Conference · Fri Sep 01 04:00:00 EDT 1995

OSTI ID:212928

Billone, M C ^[1]

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1. Argonne National Lab., IL (United States)

The properties of tritium and helium behavior in irradiated beryllium are reviewed, along with the thermal-mechanical properties needed for ITER design analysis. Correlations are developed to describe the performance of beryllium in a fusion reactor environment. While this paper focuses on the use of beryllium as a plasma-facing component (PFC) material, the correlations presented here can also be used to describe the performance of beryllium as a neutron multiplier for a tritium breeding blanket. The performance properties for beryllium are subdivided into two categories: properties which do not change with irradiation damage to the bulk of the material; and properties which are degraded by neutron irradiation. The irradiation-independent properties described within are: thermal conductivity, specific heat capacity, thermal expansion, and elastic constants. Irradiation-dependent properties include: yield strength, ultimate tensile strength, plastic tangent modulus, uniform and total tensile elongation, thermal and irradiation-induced creep strength, He-induced swelling and tritium retention/release. The approach taken in developing properties correlations is to describe the behavior of dense, pressed S-65 beryllium -- the material chosen for ITER PFC application -- as a function of temperature. As there are essentially no data on the performance of porous and/or irradiated S-65 beryllium, the degradation of properties with as-fabricated porosity and irradiation are determined from the broad data base on S-200F, as well as other types and grades, and applied to S-65 beryllium by scaling factors. The resulting correlations can be used for Be produced by vacuum hot pressing (VHP) and cold-pressing (CP)/sintering(S)/hot-isostatic-pressing (HIP). The performance of plasma-sprayed beryllium is discussed but not quantified.

• Research Organization: Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 212928
• Report Number(s): CONF-9509218--; ON: DE96002404
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BERYLLIUM
DAMAGING NEUTRON FLUENCE
IRRADIATION
ITER TOKAMAK
MECHANICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
SWELLING
TEMPERATURE DEPENDENCE
TENSILE PROPERTIES
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR MATERIALS
TRITIUM RECOVERY