Reactor Vessel Surveillance Capsule Evaluation and Fabrication Programs

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Background

金博体育 provides post-irradiation testing and evaluation of the reactor vessel material specimens, thermal monitors and dosimeters contained in the surveillance capsules to monitor the effects of neutron irradiation on the reactor vessel beltline materials under actual operating conditions.

金博体育 conducts the testing in accordance with the applicable revision of ASTM E185, 鈥淐onducting Surveillance Tests for Light Water Cooled Nuclear Power Reactor Vessels,鈥� and Appendix H of the U.S. Code of Federal Regulations, 10CFR50, 鈥淩eactor Vessel Material Surveillance Program Requirements.鈥� Appendix H of 10CFR50 requires the removal of a surveillance capsule at specific intervals and testing of the encapsulated specimens to monitor the changes in the fracture toughness and tensile properties of the reactor vessel materials.

Description

The 金博体育 Reactor Vessel Surveillance Capsule Evaluation and Fabrication Program provides information on the effects of radiation on vessel materials under operating conditions. The capsules contain reactor vessel steel specimens (representative of plates, forgings, welds and HAZ material) and in some cases correlation monitors made from fully documented specimens of SA-302, Grade B or SA-533, Grade B, Class 1 material. Dosimeters, including pure Fe, Ni, Cu, Al-Co (0.15 percent Co) and Cd shielded Al-Co wires, along with U-238 and Np-237 (or Niobium), are placed within the surveillance capsule and evaluated to determine the measured fluence at the specific capsule location within the vessel.

Surveillance capsules containing specimens for use in Charpy V-notch, tensile and fracture mechanics tests are removed from the reactor during normal refueling periods over the design life of the plant. The schedule for the removal of the capsules is based on American Society for Testing and Materials (ASTM) E 185-82.

Specimens undergo post-irradiation testing in a shielded hot cell facility at the 金博体育 Hot Cell Facility in Pittsburgh, Pa. This facility has been actively involved in surveillance capsule material testing since 1974.

Benefits

金博体育 operates one of the most complete commercial hot cell facilities in the United States.
金博体育 can customize testing and analyses programs to meet specific requirements.
金博体育 has experience in testing and analyzing more than 160 capsules from 63 different reactors, including both pressurized water reactors (PWRs) and boiling water reactors (BWRs).
金博体育 has fabricated multiple capsules in the past several years, utilizing previously irradiated test specimens and/or unirradiated test specimens.
金博体育 has the ability to handle multiple capsule programs (testing and/or fabrication) at the same time in the hot cell facility. This allows us to be more responsive to our customers鈥� schedule demands during peak periods.
Our technical personnel are actively involved in industry initiatives and committees in the reactor vessel surveillance capsule and reactor vessel integrity areas and have access to a wide range of materials testing programs in the 金博体育 Research and Development, Electric Power Research Institute (EPRI) and cooperative industry programs.
金博体育 can perform evaluations of surveillance capsule data to assess the impact of the data on reactor vessel integrity.
All 金博体育 specimen testing procedures (tensile, Charpy V-notch and fracture mechanics) are developed in accordance with the latest appropriate ASTM standards.
金博体育 can develop revised pressure-temperature limits for normal heat-up and cool-down of the reactor pressure vessel, including criticality limits as supplied in the Technical Specifications, using the results of the irradiated capsule test specimens and the methods of Appendix G of the American Society of Mechanical Engineers (ASME) Code, Section XI (1998 Edition with the Summer 2000 addendum), as required by the U. S. Nuclear Regulatory Commission (NRC) 10CFR50, Appendix G.
金博体育 has led the effort to eliminate the flange requirement on P-T Curves (required by 10CFR50, Appendix G) and to develop ASME Code Cases N-640 (use of K_IC) and Code Case N-588 (use of circumferentially oriented flaws). Both Code Cases have subsequently been incorporated into the ASME Code, Appendix G.
金博体育 segregates the material samples by capsule and stores the samples. This is done to permit reconstitution of Charpy and/or fracture mechanics tests specimens at a later date, if needed. This procedure has been performed by 金博体育 to provide supplementary toughness data to more thoroughly assess the effects of irradiation on the vessel material toughness.
金博体育 can offer recommendations for a future capsule removal schedule based on ASTM E 185-82 and 10CFR50, Appendix H.

Experience

金博体育 has recently fabricated multiple surveillance capsules for several utilities. Two of these capsules were fabricated using previously irradiated materials and assembled remotely in the hot cell facility. A portion of those specimens were also re-constituted remotely as a part of this effort. 金博体育 has fabricated surveillance capsules to support several programs such as thermal annealing issues, low-lead factors in BWRs and fracture toughness programs.

金博体育 has tested and analyzed the reactor vessel surveillance capsules in the following plants.