Three dose calculation codes applied to neutron transport in BNCT

Juha Lampinen; Tiina Seppälä; Iiro Auterinen; Sauli Savolainen

Three dose calculation codes applied to neutron transport in BNCT

Juha Lampinen (Corresponding author), Tiina Seppälä, Iiro Auterinen, Sauli Savolainen

University of Helsinki

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

Abstract

The three dimensional BNCT_Rtpe/rtt.MC is used for treatment planning in the proposed patient irradiations at the Finnish boron neutron capture therapy (BNCT) facility FiR 1. Two other radiation transport calculation codes used mainly in the characterization of the treatment beam, are DORT (Two-Dimensional Discrete Ordinates Transport Code) and MCNP (Monte Carlo N-Particle Transport Code System).

Original language	English
Title of host publication	Frontiers in Neutron Capture Therapy
Subtitle of host publication	Proceedings of the 8th International Symposium on Neutron Capture Therapy for Cancer
Editors	M. Frederick Hawthorne, Kenneth Shelly, Richard J. Wiersema
Place of Publication	Boston
Publisher	Springer
Pages	213-217
Volume	2
ISBN (Electronic)	978-1-4615-1285-1
ISBN (Print)	978-1-4613-5478-9
Publication status	Published - 2001
MoE publication type	A4 Article in a conference publication
Event	8th International Symposium on Neutron Capture Therapy for Cancer - Los Angeles, United States Duration: 13 Aug 1998 → 18 Aug 1998

Conference

Conference	8th International Symposium on Neutron Capture Therapy for Cancer
Country/Territory	United States
City	Los Angeles
Period	13/08/98 → 18/08/98

Access to Document

http://10.1007/978-1-4615-1285-1_27

Cite this

Lampinen, J., Seppälä, T., Auterinen, I., & Savolainen, S. (2001). Three dose calculation codes applied to neutron transport in BNCT. In M. F. Hawthorne, K. Shelly, & R. J. Wiersema (Eds.), Frontiers in Neutron Capture Therapy: Proceedings of the 8th International Symposium on Neutron Capture Therapy for Cancer (Vol. 2, pp. 213-217). Springer. http://10.1007/978-1-4615-1285-1_27

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title = "Three dose calculation codes applied to neutron transport in BNCT",

abstract = "The three dimensional BNCT_Rtpe/rtt.MC is used for treatment planning in the proposed patient irradiations at the Finnish boron neutron capture therapy (BNCT) facility FiR 1. Two other radiation transport calculation codes used mainly in the characterization of the treatment beam, are DORT (Two-Dimensional Discrete Ordinates Transport Code) and MCNP (Monte Carlo N-Particle Transport Code System).",

author = "Juha Lampinen and Tiina Sepp{\"a}l{\"a} and Iiro Auterinen and Sauli Savolainen",

year = "2001",

language = "English",

isbn = "978-1-4613-5478-9",

volume = "2",

pages = "213--217",

editor = "Hawthorne, {M. Frederick} and Kenneth Shelly and Wiersema, {Richard J.}",

booktitle = "Frontiers in Neutron Capture Therapy",

publisher = "Springer",

address = "Germany",

note = "8th International Symposium on Neutron Capture Therapy for Cancer ; Conference date: 13-08-1998 Through 18-08-1998",

}

Lampinen, J, Seppälä, T, Auterinen, I & Savolainen, S 2001, Three dose calculation codes applied to neutron transport in BNCT. in MF Hawthorne, K Shelly & RJ Wiersema (eds), Frontiers in Neutron Capture Therapy: Proceedings of the 8th International Symposium on Neutron Capture Therapy for Cancer. vol. 2, Springer, Boston, pp. 213-217, 8th International Symposium on Neutron Capture Therapy for Cancer, Los Angeles, California, United States, 13/08/98. <http://10.1007/978-1-4615-1285-1_27>

Three dose calculation codes applied to neutron transport in BNCT. / Lampinen, Juha (Corresponding author); Seppälä, Tiina; Auterinen, Iiro et al.
Frontiers in Neutron Capture Therapy: Proceedings of the 8th International Symposium on Neutron Capture Therapy for Cancer. ed. / M. Frederick Hawthorne; Kenneth Shelly; Richard J. Wiersema. Vol. 2 Boston: Springer, 2001. p. 213-217.

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

TY - GEN

T1 - Three dose calculation codes applied to neutron transport in BNCT

AU - Lampinen, Juha

AU - Seppälä, Tiina

AU - Auterinen, Iiro

AU - Savolainen, Sauli

PY - 2001

Y1 - 2001

N2 - The three dimensional BNCT_Rtpe/rtt.MC is used for treatment planning in the proposed patient irradiations at the Finnish boron neutron capture therapy (BNCT) facility FiR 1. Two other radiation transport calculation codes used mainly in the characterization of the treatment beam, are DORT (Two-Dimensional Discrete Ordinates Transport Code) and MCNP (Monte Carlo N-Particle Transport Code System).

AB - The three dimensional BNCT_Rtpe/rtt.MC is used for treatment planning in the proposed patient irradiations at the Finnish boron neutron capture therapy (BNCT) facility FiR 1. Two other radiation transport calculation codes used mainly in the characterization of the treatment beam, are DORT (Two-Dimensional Discrete Ordinates Transport Code) and MCNP (Monte Carlo N-Particle Transport Code System).

M3 - Conference article in proceedings

SN - 978-1-4613-5478-9

VL - 2

SP - 213

EP - 217

BT - Frontiers in Neutron Capture Therapy

A2 - Hawthorne, M. Frederick

A2 - Shelly, Kenneth

A2 - Wiersema, Richard J.

PB - Springer

CY - Boston

T2 - 8th International Symposium on Neutron Capture Therapy for Cancer

Y2 - 13 August 1998 through 18 August 1998

ER -

Three dose calculation codes applied to neutron transport in BNCT

Abstract

Conference

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