Published 2018 | Version v1
Book

Coupled modeling of NPPs: evolution, current trends and future prospects

  • 1. Atomic Energy Regulatory Board, Mumbai (India)

Description

The foundation pillar in the peaceful utilization of fission nuclear power has always been the strong emphasis on nuclear safety. Safety has been accomplished through in-depth review of design and operations, incorporation of findings from safety R and D worldwide and improvement in methods of evaluation. In the entire chain of safety process, safety analysis has been a vital link which provides an estimation of the capability of the nuclear systems to control or accommodate departures from normal operation or postulated malfunctions or failures. Safety analysis is performed using numerical simulation tools (computer codes) which have evolved gradually in terms of accuracy and complexity over the past five decades. As a conventional practice, problem specific models addressing limited physical phenomenon were developed and used during design and analysis of present generation nuclear reactors. These code were based on strong emphasize on single physic phenomenon and they were improved and refined thoroughly in that dimension. The talk will present an overview of present generation best estimate coupled computing tools for NPPs which include mostly neutronics/thermal-hydraulics coupling into reactor core on assembly/channel basis

Part of:
Proceedings of the symposium on advanced sensors and modeling techniques for nuclear reactor safety

Additional details

Publishing Information

Publisher
Indian Institute of Technology Bombay
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the symposium on advanced sensors and modeling techniques for nuclear reactor safety
Imprint Pagination
[69 p.]
Journal Page Range
[1 p.]

Conference

Title
Symposium on advanced sensors and modeling techniques for nuclear reactor safety
Dates
15-20 Dec 2018
Place
Mumbai (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
50073607
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; FAILURE MODE ANALYSIS; NUCLEAR FACILITIES; REACTOR CORES; SAFETY ANALYSIS; THERMAL HYDRAULICS
Descriptors DEC
FLUID MECHANICS; HYDRAULICS; MECHANICS; REACTOR COMPONENTS; SIMULATION; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS

Optional Information