Validation of NECP-Bamboo with BEAVRS and AP1000 measurements
Creators
- 1. School of Nuclear Science and Technology, Xi'an Jiaotong University (China)
- 2. Nuclear Power Operation Research Institute (China)
- 3. Sanmen Nuclear Power Co., Ltd (China)
- 4. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China (China)
Description
Highlights: • A two-step code validated by both 2nd and 3rd Gen commercial PWR measurements. • A power history simplification method proposed for fast load-following simulation. • A detailed power history following simulation has been done for AP1000. PWR-core fuel management code system NECP-Bamboo has been validated by about one hundred commercial PWR-core cycles including both the Second and Third Generations such as Chinese Nuclear Power CNP300 and CNP600, Chinese Pressurized Reactor CPR1000 and ACPR1000, France Framatome M310 and European Pressurized Reactor (EPR), USA Westinghouse AP1000, Chinese CAP1400 and Hualong-1, etc. Among those, the last four belong to the Third Generation PWRs. Besides, BEAVRS is the first worldwide well-known international benchmark that provides a complete two-cycle description of a commercial PWR-core, including detailed operating data and measurements, while the Unit 1 of Sanmen Nuclear Power Plant (NPP) in mainland China is the worldwide first AP1000 core. Thus, in this paper, measurements of these two PWR-cores were chosen to validate the code NECP-Bamboo, including critical boron concentration (CBC), control rod worth, temperature coefficient, detector response and boron letdown curve. Satisfying agreements have been found between the simulation with NECP-Bamboo and the corresponding measurements.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2021.111110Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2021.111110;
- PII
- S0029549321000625;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 376
- Journal Page Range
- vp.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54014766
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- BENCHMARKS; BORON; COMPUTERIZED SIMULATION; CONTROL ROD WORTHS; EPR TYPE REACTORS; FUEL MANAGEMENT; NUCLEAR INDUSTRY; NUCLEAR POWER; NUCLEAR POWER PLANTS; TEMPERATURE COEFFICIENT
- Descriptors DEC
- ELEMENTS; ENRICHED URANIUM REACTORS; INDUSTRY; MANAGEMENT; NUCLEAR FACILITIES; NUCLEAR MATERIALS MANAGEMENT; POWER; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTIVITY COEFFICIENTS; REACTORS; SEMIMETALS; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2021 Elsevier B.V. All rights reserved.