ML20153A360

From kanterella
Jump to navigation Jump to search
Transmittal of ASME Section III, Division 5 Design Tool for Advanced Non-Light Water Reactor High Temperature Metallic Components
ML20153A360
Person / Time
Issue date: 06/03/2020
From: Louise Lund
Office of Nuclear Regulatory Research
To: John Monninger
Office of Nuclear Reactor Regulation
J. Pohler
Shared Package
ML20153A359 List:
References
Download: ML20153A360 (3)


Text

June 3, 2020 MEMORANDUM TO:

John Monninger, Director Division of Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation FROM:

Louise Lund, Director /RA Jeremy Bowen for/

Division of Engineering Office of Nuclear Regulatory Research

SUBJECT:

TRANSMITTAL OF ASME SECTION III, DIVISION 5 DESIGN TOOL FOR ADVANCED NON-LIGHT WATER REACTOR HIGH TEMPERATURE METALLIC COMPONENTS The Office of Nuclear Regulatory Research (RES) has completed development of a tool that executes the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section III, Division 5 (Section III-5) design rules for high temperature metallic components. The tool was developed under a contract with Argonne National Laboratory (ANL).

The development of the tool is in accordance with NRC Non-Light Water Reactor Near-Term Implementation Action Plans (ADAMS Accession No. ML17165A069) Strategy 2:

Acquire/develop sufficient computer codes and tools to perform non-light water reactor (LWR) regulatory reviews. Specifically, under Strategy 2, Contributing Activity No. 2.29 is to assess the performance needs and issues for structural materials to be used in non-LWRs. The assessment will include the state-of-the-knowledge, ongoing domestic and international research, applicable international operational experience, codes and standards activities, gaps in knowledge, data, and assessment tools. In addition, Strategy 2, Contributing Activity No.

2.31 is to support the development of a draft regulatory framework for materials-related issues (relevant Standard Review Plan (SRP) chapters, guidance, etc.) for non-LWRs.

The development of the tool is also consistent with NRC Non-Light Water Reactor Near-Term Implementation Action Plans Strategy 4, Facilitate industry codes and standards needed to support the non-LWR life cycle (including fuels and materials). Strategy 4 identifies the need for codes for high-temperature materials for operating conditions well above the temperatures encountered in LWR operating conditions.

CONTACT:

Jeffrey Poehler, RES/DE/CIB 301-415-8353

J. Monninger 2

The tool consists of scripts written in the Python code, an open-source computer language. The Python scripts are to be run in conjunction with the Anaconda Distribution 3.7 software, which is publicly available for download at https://www.anaconda.com/products/individual and is approved in the NRC Technical Requirements Manual (TRM). Please contact the NRC help desk to install the Anaconda Distribution/Python 3.7 software on an NRC computer.

The tool will be made available to the public through the NRC public website at https://www.nrc.gov/about-nrc/regulatory/research/safetycodes.html#mpc.

Members of the public could obtain the tool will be required to fill out a nondisclosure agreement form, following which, a cognizant staff will forward the user a link to download the tool. The downloadable package contains the Python scripts, user manuals, and Excel data files containing examples that can be run using the tool. NRC staff who wish to download the tool may do so using the link in the enclosure.

The tool facilitates checking a design for an advance reactor component against all the Section III-5, Subsection HB, Subpart B (HBB) design criteria for primary load limits, strain limits, and creep-fatigue damage. Applied stresses determined using any commercial finite element analysis software can be entered in an Excel spreadsheet, which is then read by the tools and checked against the variousSection III, Division 5 design criteria. The tools will implement the automatic design evaluation for the Section III-5 rules for elastic analysis and the Code Case N-861 and N-862 rules for elastic-perfectly plastic (EPP) analysis, but do not implement the Section III-5 rules for design by inelastic analysis.

Training has been conducted for NRR and RES staff on a beta version of tools, during two sessions on January 28-29 and February 26-27, 2020.

If additional information is required, please contact Jeffrey Poehler of my staff at 301-415-8353 or jeffrey.poehler@nrc.gov.

Enclosure:

Link to Download the tool for NRC staff

J. Monninger 3

SUBJECT:

TRANSMITTAL OF ASME SECTION III, DIVISION 5 DESIGN TOOL FOR ADVANCED NON-LIGHT WATER REACTOR HIGH TEMPERATURE METALLIC COMPONENTS DISTRIBUTION:

J. Monninger, NRR B. Harris, NRR M. Hayes, NRR J. Segala, NRR B. Beasley, NRR L. Lund, RES J. Bowen, RES S. Frankl, RES R. Iyengar, RES R. Tregoning, RES K. Manoly, RES D. Rudland, RES ADAMS Package Accession No.: ML20153A359 OFFICE RES/DE RES/DE RES/DE NAME J. Poehler R. Iyengar JB for L. Lund DATE 06/03/2020 06/03/2020 06/03/2020 OFFICIAL RECORD COPY

.