Published November 2008 | Version v1
Journal article

Development and application of the PBMR fission product release calculation model

  • 1. PBMR, 1279 Mike Crawford Avenue, Centurion 0046 (South Africa)

Description

At PBMR, long-lived fission product release from spherical fuel spheres is calculated using the German legacy software product GETTER. GETTER is a good tool when performing calculations for fuel spheres under controlled operating conditions, including irradiation tests and post-irradiation heat-up experiments. It has proved itself as a versatile reactor analysis tool, but is rather cumbersome when used for accident and sensitivity analysis. Developments in depressurized loss of forced cooling (DLOFC) accident analysis using GETTER led to the creation of FIssion Product RElease under accident (X) conditions (FIPREX), and later FIPREX-GETTER. FIPREX-GETTER is designed as a wrapper around GETTER so that calculations can be carried out for large numbers of fuel spheres with design and operating parameters that can be stochastically varied. This allows full Monte Carlo sensitivity analyses to be performed for representative cores containing many fuel spheres. The development process and application of FIPREX-GETTER in reactor analysis at PBMR is explained and the requirements for future developments of the code are discussed. Results are presented for a sample PBMR core design under normal operating conditions as well as a suite of design-base accident events, illustrating the functionality of FIPREX-GETTER. Monte Carlo sensitivity analysis principles are explained and presented for each calculation type. The plan and current status of verification and validation (V and V) is described. This is an important and necessary process for all software and calculation model development at PBMR.

Part of:
3. International Topical Meeting on High Temperature Reactor Technology

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2008.02.008;
PII
S0029-5493(08)00141-6;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
238
Journal Issue
11
Journal Page Range
p. 3092-3101
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
3. international topical meeting on high temperature reactor technology
Acronym
HTR-2006
Dates
1-5 Oct 2006
Place
Johannesburg (South Africa)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
40053128
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; COOLING; DESIGN; DESIGN BASIS ACCIDENTS; FISSION PRODUCT RELEASE; FUEL ELEMENTS; HEAT; IRRADIATION; MONTE CARLO METHOD; SENSITIVITY ANALYSIS; SPHERICAL CONFIGURATION; VALIDATION; VERIFICATION
Descriptors DEC
ACCIDENTS; CALCULATION METHODS; CONFIGURATION; ENERGY; REACTOR ACCIDENTS; REACTOR COMPONENTS; TESTING

Optional Information

Copyright
Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.