Engineering topics

Martinez, Oscar A.

Publications and source records attributed to Martinez, Oscar A..

6 records

DOE OSTI2022

Test Report for DPP-1 Regulatory Compliance Testing. Volume 1 - Main Report

Consolidated Nuclear Security, LLC (CNS), the management and operating contractor for the Y-12 National Security Complex (Y-12) for the National Nuclear Security Administration (NNSA), is currently responsible for the regulatory testing of a new Type B fissile material shipping package called the Defense Programs Package (DPP)-1. The DPP-1 is a drum packaging with an inner liner and a removable lid. Both the drum body and the lid are filled with an impact-limiting, thermal-insulating material that protects the inner containment vessel (CV) during normal conditions of transport (NCT) and hypothetical accident conditions (HAC) as defined by 10 US code of Federal Regulations (CFR) 71. In fiscal year 2021, the Oak Ridge National Laboratory (ORNL) Package Testing Program (PTP), located at the National Transportation Research Center (NTRC), conducted Type B performance tests as prescribed in Title 10 Code of Federal Regulations Part 71 (10 CFR 71) on seven DPP-1 prototype units. This test report documents test unit (TU) preparation, pretest condition, conditioning of each TU, NCT and HAC testing, and posttest measurements and observations made of the damage resulting from these tests.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

DOE OSTI2020

Test Report for the Qualification Testing of the ORNL-SFC-W-1 Special Form Capsule

Three prototypes the ORNL-SFC-W-1 special form capsules (SFCs) of the same design were evaluated to determine if the requirements of Title 49, Code of Federal Regulations (CFR), Part 173.469, Tests for Special Form Class 7 (Radioactive) Materials, were met. The results of the special form tests are documented in this test report. This report describes the special form testing activities performed on the three ORNL-SFC-W-1 capsules. The test units were designated as TU-1, TU-2 and TU-3. TU-1 was subjected to leak testing, impact testing and percussion testing. TU-1 was leak tested using the leak rate test specified in 49 CFR 173.469(a)(4)(i). The impact test was conducted according to the requirements in 49 CFR 173.469 (b)(1). The percussion test that was carried out on TU-1 was conducted in accordance with 49 CFR 173.469 (b)(2). Both TU-2 and TU-3 were subjected to a leak rate test as specified in 173.469(a)(4)(i) and a heat test as specified in 49 CFR 173.469(b)(4). Each test unit was leak tested before and after these respective tests. The leak rate tests performed were helium back-pressure tests and bubble tests as specified in American National Standards Institute (ANSI) N14.5-2014.The measured leak rates were converted to standard condition leak rates as specified in American Society for Testing and Measurement (ASTM) E 493. The determined standardized leak rates obtained from the test and the calculations for all the test units met the requirements for special form certification. The testing was performed under the direction of the Oak Ridge National Laboratory (ORNL) Package Testing Program (PTP).

42 ENGINEERING↗

DOE OSTI2019

LANL NPB Project: Ion Source Selection and Development Path

The ORNL team will provide LANL with a scoping / feasibility study of H - sources which could potentially be developed to approach the goal of producing a single high-duty-factor H - beam of up to ~100 mA suitable for acceleration by an RFQ. Currently, no existing H - sources have been shown to operate anywhere near this goal so the study will focus on identifying the most promising approach and define the existing option space. Attention will be given to source concepts which are most likely to be scalable to continuous beam operation while offering lower-risk, lower duty-factor or beam current operation in the shorter term. The study will discuss the technology within this option space, tradeoffs and identify the best path forward. Once the best option is identified, an estimate of the expected output emittance, beam current, achievable beam duty-factor, hydrogen and cesium consumption rates, physical size and weight estimates of the source and supporting subsystems will be provided. This work will lay the foundation for developing a conceptual source design in Development 2 which will inform an actual mechanical design that will be used to either construct a prototype source or modify an existing source as part of a future technology development program for the project. The relative technology development risk and mitigations would also be defined for the candidate ion source technologies for a TRL 5 demonstration. Risk analysis for later TRL 6 phases and beyond would be part of a later phase of the project.

43 PARTICLE ACCELERATORS↗

DOE OSTI2018

Test Report of Special Form Qualification Testing for the ORNL U ZiPCAN, Rev. 1

This report describes the special form testing activities performed on the two ZiPCans. One prototype test unit was subjected to the tests stipulated by International Standards Organization (ISO) 2919:1999(E) Class 4 impact test, along with the leak rate test specified in 49 CFR 173.469(a)(4)(i). The other test unit was subjected to a leak rate test as specified in 173.469(a)(4)(i) and a heat test as specified in 49 CFR 173.469(b)(4).

42 ENGINEERING↗

DOE OSTI2018

Temperature Monitoring and Data-logging System Operating Manual

The MD-2 LabVIEW program is designed to monitor and store the temperature data from the MD-2 Compliance Testing. The program allows the user to easily configure and track data. A configuration file can be modified and stored to provide the setup parameters. It provides a user interface that easily informs the user about unforeseen anomalies.

42 ENGINEERING↗

DOE OSTI2017

Test Report of Special Form Qualification Testing for the ORNL U ZipCan

This test report describes the special form testing activities performed on the two ZiPCans. One prototype test unit was subjected to the tests stipulated by 10 CFR 71.75 (d)(1)(i), ISO 2919:1999(E) Class 4 impact test, along with the leak rate test specified in 49 CFR 173.469(a)(4)(i). The other test unit was subjected to a leak rate test as specified in 173.469(a)(4)(i) and a heat test as specified in 49 CFR 173.469 (b)(4). Each test unit was leak tested before and after these respective tests. The leak rate tests performed were helium back-pressure tests and bubble tests, as specified in ANSI N14.5-2014.The measured leak rates were converted to standard condition leak rates as specified in ASTM E 493. The determined standardized leak rates from the test and calculation for both test units met the requirements for special form certification.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗