Analytical and statistical calculation of gamma dose rate for the accident of losing the shield for Tehran Research Reactor

Farshid Tabbakh; Azim Ahmadinyar

doi:10.1088/1674-1137/32/11/006

Chinese Physics C> 2008, Vol. 32> Issue(11) : 877-881 DOI: 10.1088/1674-1137/32/11/006

Analytical and statistical calculation of gamma dose rate for the accident of losing the shield for Tehran Research Reactor

Farshid Tabbakh ^, ,
Azim Ahmadinyar

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Abstract：
In this paper we study the analytical and statistical results of estimating the gamma dose rate at pool access floor in TRR when the core shield accidentally decreases to some non-permitted levels. Due to the risk of experimental techniques, we use the analytical and statistical methods. In normal conditions (no risk), the discrepancies between experiment and two methods are justified and it is found that for such problems we have to normalize these methods to experimental results as follows: the analytical method by factor 0.13 and MCNP by 1.7.

References

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. A M F. Atomics Industrial Products Group. Safety Analy-sis Report for Tehran Research Reactor. 19662. Nuclear Research Center, Atomic Energy Organization ofIran. Safety Analysis Report for Tehran Research Reactor(TRR). 20023. Harmon C D, Busch R D. Criticality Calculation with MCNP5: A Primer. Los Alamos National Laboratory, 20064. OAK Ridge National Laboratory. Monte Carlo N-Particle Transport Code System (MCNP4C). Los Alamos National Laboratory, 20005. ANSI/ANS-6.4.3. Gamma-Ray Attenuation Coefficient and Buildup Factor for Engineering Materials. American Nuclear Society, 19916. ANSI/ANS-6.1.1. Neutron and Gamma-Ray Fluence-to-Dose Factors. American Nuclear Society, 19917. Chilton A B. Principles of Radiation Shielding. Prentice-Hall, Inc., 10848. Radulescu G. Automated Variance Reduction for MonteCarlo Shielding Analyses with MCNP. University of Texasat Austin, 20039. Kaynia N, Firoozfar N. Water Quality Control for Tehran Research Reactor, TRR-REP-CHEM-05. Nuclear Research Center, Atomic Energy Organization of Iran, 200710. Blanchard M, Wilson P. Characterization of Gamma Ra-diation Fields at the University of Wisconsin Nuclear Reactor Lab - 1MW TRIGA. University of Wisconsin.www.engr.utexas.edu/trtr/agenda/documents/Blanchard-CaF.pdf

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Farshid Tabbakh and Azim Ahmadinyar. Analytical and statistical calculation of gamma dose rate for the accident of losing the shield for Tehran Research Reactor[J]. Chinese Physics C, 2008, 32(11): 877-881. doi: 10.1088/1674-1137/32/11/006

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Received: 2008-01-15
Revised: 2008-07-02

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通讯作者: 陈斌, [email protected]

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沈阳化工大学材料科学与工程学院沈阳 110142

Analytical and statistical calculation of gamma dose rate for the accident of losing the shield for Tehran Research Reactor

Corresponding author: Farshid Tabbakh,

Received Date: 2008-01-15

Accepted Date: 2008-07-02

Available Online: 2008-11-05

Abstract:

In this paper we study the analytical and statistical results of estimating the gamma dose rate at pool access floor in TRR when the core shield accidentally decreases to some non-permitted levels. Due to the risk of experimental techniques, we use the analytical and statistical methods. In normal conditions (no risk), the discrepancies between experiment and two methods are justified and it is found that for such problems we have to normalize these methods to experimental results as follows: the analytical method by factor 0.13 and MCNP by 1.7.

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Analytical and statistical calculation of gamma dose rate for the accident of losing the shield for Tehran Research Reactor

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