Published November 2015 | Version v1
Journal article

Solution of PHWR 3D kinetics benchmark using TRIKIN code

  • 1. Nuclear Safety Analysis Division, Atomic Energy Regulatory Board, Anushaktinagar, Niyamak Bhavan, Mumbai 400094 (India)
  • 2. Department of Mechanical Engineering, College of Engineering Pune, Shivajinagar, Pune 411005 (India)

Description

Highlights: •This paper describes space-time kinetics formulation for transient analysis of Pressurized Heavy Water Reactors. •Improved Quasistatic (IQS) approximation has been used for factorization of neutron fluxes. •3D kinetics Benchmark problem (AECL-7236) of PHWR has been analyzed. •Obtained TRIKIN results are in good agreement with benchmark solution, demonstrating space-time capability of code for PHWRs. -- Abstract: Scaling up of core sizes beyond present generation has rendered renewed topicality to space-time kinetics and relevant safety research. Detailed computational codes to solve transient neutron diffusion equation for the highest level of approximation including core thermal as well as system feedbacks are being established worldwide. Consistent with this objective a general purpose 3D kinetics code 'TRIKIN' has been developed in the Atomic Energy Regulatory Board (AERB) and the Indian Institute of Technology Bombay, India to carry out transient analysis for a variety of power reactors. Code has been validated against a series of international benchmark problems for light water reactors. This paper presents an extension of the validation array of the TRIKIN code by solving a 3D kinetics PHWR benchmark problem (AECL-7236). A brief overview of space time kinetics methods is presented. Detailed numerical scheme of improved quasistatic (IQS) method to solve transient neutron diffusion equations, adopted in TRIKIN code has been described. Description of 3D kinetics PHWR benchmark problem and its solution using TRIKIN code has been presented. TRIKIN results have shown good agreement with benchmarks results, demonstrating excellent space-time kinetics capability of the code for PHWR type reactors.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.pnucene.2015.06.020

Additional details

Identifiers

DOI
10.1016/j.pnucene.2015.06.020;
PII
S0149197015300251;

Publishing Information

Journal Title
Progress in Nuclear Energy
Journal Volume
85
Journal Page Range
p. 200-212
ISSN
0149-1970

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
51027571
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
KINETICS; NEUTRON FLUX; PHWR TYPE REACTORS; POWER REACTORS; SPACE-TIME; WATER COOLED REACTORS; WATER MODERATED REACTORS
Descriptors DEC
HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; RADIATION FLUX; REACTORS

Optional Information

Notes
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