Published August 2019 | Version v1
Miscellaneous Open

A deterministic model for criticality and rod worth analysis of the Dalat nuclear research reactor with HEU fuel

  • 1. University of Science, Vietnam National University, Ho Chi Minh City (Viet Nam)
  • 2. Duy Tan University, Ho Chi Minh City (Viet Nam)
  • 3. Nuclear Research Institute, Dalat (Viet Nam)
  • 4. Ho Chi Minh City University of Technology and Education, Ho Chi Minh City (Viet Nam)

Description

This paper presents the development and verification of a deterministic model using the SRAC code system for analysing the criticality and control rod worth of the Dalat Nuclear Research Reactor (DNRR). Numerical calculations were performed based on seven core configurations established experimentally during the startup period of the DNRR. Comparison of the results with MCNP5 calculations and with the measurement data was conducted. The impact of various nuclear data libraries (ENDF/B and JENDL) on the criticality and control rod worth analysis was also investigated.(author)

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Part of:
Vietnam Conference on Nuclear Science and Technology VINANST-13. Agenda and Abstracts

Additional details

Additional titles

Original title (Vietnamese)
Mo hinh tat dinh trong phan tich toi han va dac trung tich phan cua thanh dieu khien cua lo phan ung hat nhan Da Lat su dung nhien lieu HEU

Publishing Information

Imprint Title
Vietnam Conference on Nuclear Science and Technology VINANST-13. Agenda and Abstracts
Imprint Pagination
266 p.
Journal Page Range
8 p.
Report number
INIS-VN--004

Conference

Title
13. Vietnam Conference on Nuclear Science and Technology
Original Conference Title
Hoi nghi Khoa hoc va Cong nghe Hat nhan Toan quoc lan thu 13
Acronym
VINANST-13
Dates
7-9 Aug 2019
Place
Ha Long City, Quang Ninh (Viet Nam)

INIS

Country of Publication
Viet Nam
Country of Input or Organization
Viet Nam
INIS RN
51079275
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; CONTROL ROD WORTHS; CRITICALITY; DETERMINISTIC ESTIMATION; MONTE CARLO METHOD; RESEARCH REACTORS
Descriptors DEC
CALCULATION METHODS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION

Optional Information

Notes
16 refs, 6 figs, 2 tabs; This record replaces 50071460 Imprint:Conference program and paper abstracts only