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Calculation of radiation fields inside and outside the NET cryostat/biological shield during operation

Abstract

The calculations were performed using both the Monte Carlo code MCNP and the 2D discrete ordinates neutron/{gamma} transport code DORT. Consistent nuclear data were used: For the Monte Carlo calculations data were taken from the EFF-1.3 library, for the discrete ordinates calculations data were taken from the MAT175 library. Both libraries are based on the JEF/EFF-1 evaluation. Care was taken to model the 2.0 cm wide gaps between two blanket segments, as the neutron flux behind the vacuum vessel is largely determined by neutrons streaming through these gaps. The resulting neutron- and {gamma}-flux spectra are in excellent agreement up to the end of the cryostat. It is noted, that at this position the attenuation of the neutron flux is about 11 orders of magnitude. Due to precautions in the Monte Carlo calculations the uncertainty in neutron- and {gamma}-flux spectra calculated by MCNP is only small: The uncertainty in the integrated neutron spectrum amounts to approximately 15% at the end of the cryostat. Also the dose-rates as calculated by MCNP and DORT agree well. Differences occur when heating data are compared. This is clearly due to the different way in which nuclear heating is treated in MCNP (direct calculation of heating)  More>>
Publication Date:
Sep 01, 1993
Product Type:
Conference
Report Number:
ECN-RX-93-094; CONF-920930-
Reference Number:
SCA: 700450; PA: NLN-94:0F4227; EDB-94:066231; SN: 94001185547
Resource Relation:
Conference: 17. symposium on fusion technology (SOFT-17),Rome (Italy),14-18 Sep 1992; Other Information: PBD: Sep 1993
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; NET TOKAMAK; BIOLOGICAL SHIELDS; BREEDING BLANKETS; CRYSTALS; RADIATION STREAMING; NEUTRON TRANSPORT THEORY; MONTE CARLO METHOD; COMPUTER CALCULATIONS; DISCRETE ORDINATE METHOD; NEUTRON FLUX; GAMMA SPECTRA; NEUTRON SPECTRA; DOSE RATES; OPERATION; 700450; BLANKETS AND COOLING SYSTEMS
OSTI ID:
10142607
Research Organizations:
Netherlands Energy Research Foundation (ECN), Petten (Netherlands)
Country of Origin:
Netherlands
Language:
English
Other Identifying Numbers:
Other: ON: DE94758551; TRN: NL94F4227
Availability:
OSTI; NTIS
Submitting Site:
NLN
Size:
21 p.
Announcement Date:
Jul 05, 2005

Citation Formats

Hogenbirk, A, and Verschuur, K A. Calculation of radiation fields inside and outside the NET cryostat/biological shield during operation. Netherlands: N. p., 1993. Web.
Hogenbirk, A, & Verschuur, K A. Calculation of radiation fields inside and outside the NET cryostat/biological shield during operation. Netherlands.
Hogenbirk, A, and Verschuur, K A. 1993. "Calculation of radiation fields inside and outside the NET cryostat/biological shield during operation." Netherlands.
@misc{etde_10142607,
title = {Calculation of radiation fields inside and outside the NET cryostat/biological shield during operation}
author = {Hogenbirk, A, and Verschuur, K A}
abstractNote = {The calculations were performed using both the Monte Carlo code MCNP and the 2D discrete ordinates neutron/{gamma} transport code DORT. Consistent nuclear data were used: For the Monte Carlo calculations data were taken from the EFF-1.3 library, for the discrete ordinates calculations data were taken from the MAT175 library. Both libraries are based on the JEF/EFF-1 evaluation. Care was taken to model the 2.0 cm wide gaps between two blanket segments, as the neutron flux behind the vacuum vessel is largely determined by neutrons streaming through these gaps. The resulting neutron- and {gamma}-flux spectra are in excellent agreement up to the end of the cryostat. It is noted, that at this position the attenuation of the neutron flux is about 11 orders of magnitude. Due to precautions in the Monte Carlo calculations the uncertainty in neutron- and {gamma}-flux spectra calculated by MCNP is only small: The uncertainty in the integrated neutron spectrum amounts to approximately 15% at the end of the cryostat. Also the dose-rates as calculated by MCNP and DORT agree well. Differences occur when heating data are compared. This is clearly due to the different way in which nuclear heating is treated in MCNP (direct calculation of heating) and DORT (kerma factors used; including radioactive decay contributions). (orig.)}
place = {Netherlands}
year = {1993}
month = {Sep}
}